Text

(Section 8) Sequoyah Initial Exam 2016-301 Final RO Written Exam
	ML16110A027
Person / Time
Site:	Sequoyah
Issue date:	04/18/2016
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-327/16-301, 50-328/16-301
	Download: ML16110A027 (84)
	v • d • e

ES4OI Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: Facility/Unit: Sequoyah Station Units I & 2 Region: i II X Ill IV ReactorType:WXCEEIBWEIGEEI Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after the examination begins.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicants Signature Results Examination Value Points Applicants Score Points Applicants Grade Percent Q]

cktce,C iS ,,2 B Cc-w

Name: ________________________________ 1603 NRC RO Exam Form: 0 Version: 0

1. Given the following plant conditions:

- Unit 2 was at 60% power when a reactor trip occurred.

- After the crew has completed the immediate actions of E-0, "Reactor Trip or Safety Injection," the OATC observed the following on Annunciator Panel 2-XA-55-4D, "Reactor First Out":

- LS-3-97B, "STM GEN LOOP 3 LEVEL LOW-LOW REACTOR TRIP" window lit and NOT flashing.

- "P-9 TURBINE TRIP REACTOR TRIP" window flashing.

Which ONE of the following identifies the cause of the reactor trip and the status of the Reactor Trip First Out Panel?

A. The reactor tripped due to the turbine trip; The Reactor Trip First Out panel has been acknowledged, but NOT reset.

B. The reactor tripped due to the turbine trip; The Reactor Trip First Out panel has NOT been acknowledged and the SG Low-Low level window came in after the reactor trip occurred.

C. The reactor tripped due to the SG low level; The Reactor Trip First Out panel has been acknowledged, but NOT reset.

D. The reactor tripped due to the SG low level; The Reactor Trip First Out panel has been acknowledged and the P-9 Turbine Trip Reactor Trip window came in after the panel was acknowledged.

Friday, March 04, 2016 10:17:05 AM 1

1603 NRC RO Exam

2. Given the following plant conditions:

- Unit 2 is manually tripped from 100% power due to rapidly lowering PZR level and pressure.

- The crew has entered E-1, "Loss of Reactor or Secondary Coolant"

- The crew is directed to MAINTAIN Intact S/G narrow range levels.

Which ONE of the following completes the statement below?

S/G level is required for __(1)__ events because heat removal by S/Gs __(2)__.

A. (1) SBLOCA (2) ensures no core uncovery occurs B. (1) SBLOCA (2) is needed during recovery to achieve Cold Shutdown C. (1) LBLOCA (2) ensures core exit TCs do not exceed 700°F D. (1) LBLOCA (2) is needed during recovery to achieve Cold Shutdown Friday, March 04, 2016 10:17:05 AM 2

1603 NRC RO Exam

3. Given the following plant conditions:

- Unit 1 is operating at 100% power

- Main Feed Reg valve for #2 SG fails closed

- Subsequently an automatic reactor trip signal is generated

- An ATWS is in progress

- Reactor power is at 9% and lowering

- #2 RCP Lower Motor Bearing temp is 285°F and rising rapidly.

In accordance with FR-S.1, "Nuclear Power Generation/ATWS," which ONE of the following identifies when #2 RCP can be tripped and what is the basis?

A. immediately to conserve secondary inventory B. Immediately to protect the pump for later use C. wait until below 5% reactor power to prevent fuel integrity challenge D. wait until below 5% reactor power to allow SG level to be recovered prior to securing pump.

Friday, March 04, 2016 10:17:05 AM 3

1603 NRC RO Exam

4. Given the following plant conditions:

- Both Units are at 100% power

- The "B" BAT has been removed from service due to a leak

- The "C" BAT is being placed in service on Unit 2.

- The RWST boron concentration is 2600 ppm.

Which ONE of the following identifies both:

(1) the minimum allowable "C" BAT volume and boron concentration required by TRM 8.1.1 "Boration Systems - Operating,"

and (2) the location that BAT "C" level indicator 0-LI-62-242, can be read?

REFERENCE PROVIDED A. (1) 9250 gals at 6650 ppm Boron (2) 1-M-6 ONLY B. (1) 9500 gals at 6600 ppm Boron (2) 1-M-6 ONLY C. (1) 9250 gals at 6650 ppm Boron (2) 1-M-6 and 2-M-6 D. (1) 9500 gals at 6600 ppm Boron (2) 1-M-6 and 2-M-6 Friday, March 04, 2016 10:17:05 AM 4

1603 NRC RO Exam

5. Given the following plant conditions:

- Unit 2 is in Mode 6.

- RCS drained to elevation 701 feet.

- RCS temperature is 110°F.

- Upper Internals are not installed.

- Core decay heat is approximately 5 MW.

- A total loss of RHR cooling has occurred.

Which ONE of the following identifies the minimum amount of time it will take to reach 212°F in the RCS?

Reference Provided A. 30 minutes B. 36 minutes C. 49 minutes D. 347 minutes Friday, March 04, 2016 10:17:05 AM 5

1603 NRC RO Exam

6. Given the following plant conditions:

- Unit 1 is in Mode 3 for maintenance.

- An event occurs which results in all of the following annunciators:

- "MISC EQUIP SUPPLY HEADER FLOW LOW," (M27B-B, A-3).

- "LETDOWN HX OUTLET FLOW/TEMP ABNORMAL," (M27B-B, A-5)

- "TS-62-78 LTDN HX OUTLET TO DEMIN TEMP HIGH," (M6C, A4)

- "TURB AUX OR REAC BLDG FLOODED" (M15B, D3)

Which ONE of the following identifies the cause of these alarms?

A leak on the ____ .

A. charging header B. letdown line C. "A" train of CCS D. ERCW header Friday, March 04, 2016 10:17:05 AM 6

1603 NRC RO Exam

7. Given the following plant conditions:

- Unit 2 is operating at 100% power.

- A failure of the controlling input to the Pressurizer Pressure Master Controller caused actual pressurizer pressure to increase to 2273 psig.

- The Pressurizer Pressure Master Controller, PIC-68-340A, has been placed in MANUAL.

Which ONE of the following describes the action required to return pressure to 2235 psig?

A. Raise the master controller output B. Lower the master controller output C. Raise the master controller pressure setpoint D. Lower the master controller pressure setpoint Friday, March 04, 2016 10:17:05 AM 7

1603 NRC RO Exam

8. Given the following plant conditions:

- Unit 1 is at 100% power

- SSPS testing in progress

- RTA and BYB Reactor Trip Breakers are shut

- Reactor Trip Breaker "B" is open

- Subsequently, a transient occurs that requires a reactor trip but the reactor fails to trip from the trip switch.

Which ONE of the following completes the statements below?

The RTA & BYB 125V dc trip coils failed to __(1)__ .

If only BYB is opened locally, the reactor __(2)__ trip.

A. (1) energize (2) will B. (1) energize (2) will NOT C. (1) de-energize (2) will D. (1) de-energize (2) will NOT Friday, March 04, 2016 10:17:05 AM 8

1603 NRC RO Exam

9. Given the following plant conditions:

- Unit 1 tripped from 100% power due to an inadvertent Feedwater Isolation

- 6.9 kV Shutdown Board 1A-A is deenergized and cannot be reenergized

- The 1B-B charging pump is out of service for motor bearing replacement

- All S/G NR levels are 5% and lowering

- RCS pressure is 2235 psig and stable

- The crew has not been able to establish AFW flow per E-0, "Reactor Trip or Safety Injection"

- The SRO has just announced that the Heat Sink status tree is Red Which ONE of the following identifies the action(s) the crew will take first to establish RCS cooling after entering FR-H.1, "Loss of Secondary Heat Sink?"

A. Establish flow to at least one S/G using a MFW pump B. Depressurize at least one S/G and align HPFP to the depressurized S/G(s)

C. Establish RCS feed and bleed using the 1B-B SI pump and both PZR PORVs D. Depressurize at least one S/G and establish condensate flow to the depressurized S/G(s)

Friday, March 04, 2016 10:17:05 AM 9

1603 NRC RO Exam

10. Given the following plant conditions:

- Unit 1 was operating at 100% power when a loss of all 161kv and 500kv lines occurred.

- Both 1A-A and 1B-B D/Gs failed to automatically and manually start.

- The operating crew is responding in accordance with ECA-0.0, "Loss of All AC Power"

- Subsequently off-site power has been restored to the Start Bus 1A and 1B

- Neither shutdown board is re-energized.

- The following indications are observed:

- All 480 V transformer breaker indicating lights for XFMR 1A-A, XFMR 1A1-A and XFMR 1A2-A all indicate RED

- All 480 V Transformer breaker indicating lights for XFMR 1B-B, XFMR 1B1-B and XFMR 1B2-B all indicate GREEN In accordance with ECA-0.0, which ONE of the following identifies the 6.9KV shutdown board(s) that will be energized?

A. 6.9KV Shutdown BD 1A-A, ONLY B. 6.9KV Shutdown BD 1B-B, ONLY C. Both D. Neither, until TSC evaluation Friday, March 04, 2016 10:17:05 AM 10

1603 NRC RO Exam

11. Given the following plant conditons:

- Unit 1 is operating at 100% power.

- A Loss of Vital Instrument Power Board 1-I has occurred.

- The Unit has been tripped and control of AFW to loops 1 and 2 is required.

In accordance with AOP-P.03 "Loss of Unit 1 Vital Instrument Power Board", which ONE of the following identifies the required actions to control AFW to loops 1 and 2.

__(1)__ the 1A-A MD AFW pump.

Accident Reset __(2)__ to be depressed to open loops 1 and 2 MDAFW bypass valves.

A. (1) Manually start (2) is required B. (1) Manually start (2) is NOT required C. (1) Verify AMSAC started (2) is required D. (1) Verify AMSAC started (2) is NOT required Friday, March 04, 2016 10:17:05 AM 11

1603 NRC RO Exam

12. Which ONE of the following identifies the transfer scheme associated with120VAC Vital Inverters Static Switch?

If Inverter Transfer back fails to Inverter A. AUTOMATICALLY Must be MANUALLY transferred transfers to the isolimiter back after inverter output voltage returns to normal B. AUTOMATICALLY AUTOMATICALLY transfers back transfers to the isolimiter after a time delay if inverter output voltage returns to normal C. Must be MANUALLY Must be MANUALLY transferred transferred to the isolimiter back after inverter output voltage returns to normal D. Must be MANUALLY AUTOMATICALLY transfers back transferred to the isolimiter after a time delay if inverter output voltage returns to normal Friday, March 04, 2016 10:17:05 AM 12

1603 NRC RO Exam

13. Given the following plant conditions:

- Both Units are at 100% power.

- ERCW is in normal alignment.

- Subseqently: ERCW header 1A & 2A start indicating LOW flow.

- The following MCR alarms are LIT:

MECH EQUIP SUMP LVL HI (1-M-15A, B-6)

UNIT 1 HEADER A PRESSURE LOW (0-M-27A, A-1)

UNIT 2 HEADER A PRESSURE LOW (0-M-27A, B-3)

- NO OTHER alarms are lit associated with the ERCW system.

Which ONE of the following ERCW conditions accounts for the above indications?

REFERENCE PROVIDED A. Supply header 1A/2A has ruptured in the Yard Area.

B. A discharge header has ruptured in the Yard Area.

C. A rupture has occurred upstream of the 2A strainer.

D. A rupture has occurred in the CCW Intake Pumping Station.

Friday, March 04, 2016 10:17:05 AM 13

1603 NRC RO Exam

14. Which ONE of the following completes the statement below?

The reason for the Turbine Driven AFW Pump LCVs SBO backup air supply is to allow the LCVs to be ___(1)___ and the SBO backup air supply will

___(2)___.

A. (1) OPENED (2) require manual alignment locally when needed B. (1) OPENED (2) automatically be supplied when air pressure drops below regulator setpoint C. (1) CLOSED (2) require manual alignment locally when needed D. (1) CLOSED (2) automatically be supplied when air pressure drops below regulator setpoint Friday, March 04, 2016 10:17:05 AM 14

1603 NRC RO Exam

15. Given the following plant conditions:

- Unit 1 is operating at 100% power

- Subsequently, a Loss Of Coolant Accident (LOCA) outside containment has resulted in RCS Subcooling dropping to 0°F.

- The crew has transitioned to ECA-1.2, "LOCA Outside Containment."

In accordance with ECA-1.2, which ONE of the following:

(1) is the initial mitigating strategy and (2) what would be the indication used to confirm the LOCA has been isolated?

A. (1) Verify RHR suction from RCS Isolated (2) Pressurizer level rising B. (1) Verify RHR suction from RCS Isolated (2) RCS pressure rising C. (1) Isolate RHR Cold Leg Injection (2) Pressurizer level rising D. (1) Isolate RHR Cold Leg Injection (2) RCS pressure rising Friday, March 04, 2016 10:17:05 AM 15

1603 NRC RO Exam

16. Given the following plant conditions:

- A LOCA has occurred on Unit 1.

- The crew is implementing ECA-1.1, "Loss of RHR Sump Recirculation."

Which ONE of the following completes the statement below in accordance with EPM-3-ECA-1.1, "Basis Document for ECA-1.1 Loss of RHR Sump Recirculation?"

Initiation of RCS cooldown to Cold Shutdown will be performed ___(1)___ RCS depressurization AND the reason for the RCS depressurization is ___(2)___.

___(1)___ ___(2)___

A. before to reduce the break flow B. before to refill the pressurizer C. after to reduce the break flow D. after to refill the pressurizer Friday, March 04, 2016 10:17:05 AM 16

1603 NRC RO Exam

17. Given the following plant conditions:

- Unit 2 is at 100% power.

- The TDAFW Pump is tagged out of service.

- A Loss of Feedwater causes a reactor trip.

- Coincident with the trip, 6.9KV Shutdown Board 2A-A de-energizes on fault.

Which ONE of the following identifies the SGs that will receive AFW flow and the expected flow rate to those SGs?

A. SGs 1 & 2 being fed at 220 GPM each B. SGs 1 & 2 being fed at 440 GPM each C. SGs 3 & 4 being fed at 220 GPM each D. SGs 3 & 4 being fed at 440 GPM each Friday, March 04, 2016 10:17:05 AM 17

1603 NRC RO Exam

18. Given the following plant conditions:

- Unit 1 is operating at 80% power.

- Due to grid disturbances the crew had entered AOP-P.07, "Degraded Grid Conditions or Generator Voltage Regulator Malfunction."

- Grid frequency has held steady at 59 Hz for twenty minutes.

- The Unit Supervisor directs the OATC to trip the reactor.

In accordance with AOP-P.07, "Degraded Grid Conditions or Generator Voltage Regulator Malfunction," which ONE of the following identifies the reason for this required action?

A. The Tech Spec limit for frequency on a shutdown board has been exceeded.

B. To prevent exceeding improper bearing loading and turbine misalignment.

C. The auto reactor trip setpoint for RCP underfrequency has been exceeded.

D. To prevent exceeding 25% of lifetime limit of off-frequency operation of LP turbine.

Friday, March 04, 2016 10:17:05 AM 18

1603 NRC RO Exam

19. Given the following plant conditions:

- A Reactor Trip occurred on Unit 1.

- Due to excessive RCS cooldown, the crew is implementing EA-68-4, Section 4.2, "Emergency Boration from BAT".

- After placing 1-HS-62-138A, Emergency Boration FCV in OPEN, the OATC released the handswitch after observing flow indicated on 1-FI-62-137A, Emerg Boration Flow.

- Two minutes later, the OATC observed both 1-HS-62-138A RED and GREEN lights LIT and flow stable at 50 gpm.

Which ONE of the following identifies the status of FCV-62-138, Emergency Boration FCV and the corresponding emergency boration flow rate?

FCV-62-138...

A. stopped opening when the handswitch was released and the flow rate is BELOW the minimum required.

B. stopped opening when the handswitch was released and the flow rate is ABOVE the minimum required.

C. should be full open but has stopped due to thermal overload and the flow rate is BELOW the minimum required.

D. should be full open but has stopped due to thermal overload and the flow rate is ABOVE the minimum required.

Friday, March 04, 2016 10:17:05 AM 19

1603 NRC RO Exam

20. Given the following plant conditions:

- Unit 1 is at 100% power.

- Pressurizer Level Channel Selector, 1-XS-68 339E, is in the LT-68-339 & 335 position.

- Subsequently, the REFERENCE LEG for 1-LI-68-335 develops a leak.

Which ONE of the following identifies the short term (25 to 30 min.) response to this condition?

1-LI-68-339 level indication will __(1)__ and 1-LI-68-335 level indication will__(2)__.

A. (1) Rise (2) Rise B. (1) Rise (2) Lower C. (1) Remain the same (2) Rise D. (1) Remain the same (2) Lower Friday, March 04, 2016 10:17:05 AM 20

1603 NRC RO Exam

21. Given the following plant conditions:

- Unit 2 is in Mode 6.

- The core is being off-loaded.

- It has just been identified (and verified) that the RCS boron concentration is 1975 ppm.

- The refueling boron concentration required by the COLR is 2000 ppm.

Which ONE of the following completes the statement below?

The crew is required to ...

A. initiate boration and suspend positive reactivity changes.

B. suspend core alterations and establish containment integrity.

C. initiate boration and enter AOP-M.04 "Refueling Malfunctions".

D. suspend positive reactivity changes and establish containment intergrity.

Friday, March 04, 2016 10:17:05 AM 21

1603 NRC RO Exam

22. Given the following plant conditions:

- Unit 1 was at 100% power.

- Subsequently, a Steam Generator Tube Leak develops and the crew enters AOP-R.01, Steam Generator Tube Leak.

- A unit shutdown is commenced in accordance with AOP-C.03, "Rapid Shutdown Or Load Reduction," with reactor power currently at 85%.

- Current plant conditions are:

- PZR Level is 55% and stablized

- Charging flow is 105 gpm

- RCP seal leak off is 3 gpm per pump

- RCP seal injection is 8 gpm per pump

- Letdown is isolated Which ONE of the following completes the statement below?

The estimated magnitude of the tube leak is ___(1)___ gpm and leak rate will

___(2)___ as power is reduced.

A. (1) 93 (2) lower B. (1) 93 (2) remain the same C. (1) 125 (2) remain the same D. (1) 125 (2) lower Friday, March 04, 2016 10:17:05 AM 22

1603 NRC RO Exam

23. Given the following plant conditions:

- Unit 1 reactor is at 100% power.

- Containment entry is in progress for maintenance.

- The following annunciators on 1-M12-C are received:

- LWR PERS ACCESS OUTER DR LOCK

- LWR PERS ACCESS INNER DR LOCK

- UPR/LWR AIR LOCK BREACH

- Containment pressure has equalized with the Aux. Building.

- Containment pressure currently indicates 0.18 psid.

- It is determined that the overall containment leakage rate has been exceeded.

Based on the conditions above, which ONE of the following identifies the Tech Spec(s) with actions required to be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ?

A. TS 3.6.2 CONTAINMENT AIR LOCKS, only B. TS 3.6.1 CONTAINMENT and TS 3.6.4 CONTAINMENT PRESSURE C. TS 3.6.1 CONTAINMENT and TS 3.6.2 CONTAINMENT AIRLOCKS D. TS 3.6.2 CONTAINMENT AIR LOCKS and TS 3.6.4 CONTAINMENT PRESSURE Friday, March 04, 2016 10:17:05 AM 23

1603 NRC RO Exam

24. Given the following plant conditions:

- Due to a fire, the Main Control Room has been evacuated.

- The crew has implemented AOP-C.04, "Shutdown From Auxiliary Control Room," and have commenced a cooldown of Unit 1.

Which ONE of the following identifies the required procedure actions to control PZR level within the operating band?

Charging flow will be via __(1)__ path and letdown will be via __(2)__ path.

A. (1) its normal (2) its normal B. (1) its normal (2) excess letdown C. (1) seal injection (2) its normal D. (1) seal injection (2) excess letdown Friday, March 04, 2016 10:17:05 AM 24

1603 NRC RO Exam

25. Given the following plant conditions:

- Unit 2 is operating at 100%

Which one of the following identifies...

(1) the minimum DOSE EQUIVALENT Xe-133 activity value that will require entry into AOP-R.06, "High RCS Activity,"

and (2) the reason for contacting Chemistry during performance of AOP-R.06?

A. (1) > 1200.0 microCi/gm (2) To ensure the Fuel Reliability Assessment Program is implemented.

B. (1) > 1200.0 microCi/gm (2) To recommend letdown alignment for maximizing the cleanup of the RCS.

C. (1) > 1612.6 microCi/gm (2) To recommend letdown alignment for maximizing the cleanup of the RCS.

D. (1) > 1612.6 microCi/gm (2) To ensure the Fuel Reliability Assessment Program is implemented.

Friday, March 04, 2016 10:17:05 AM 25

1603 NRC RO Exam

26. Given the following plant conditions:

- Unit 1 was operating at 100% power.

- Subsequently, the unit has experienced a reactor trip and loss of offsite power.

- The crew is performing ES-0.4, "Natural Circulation Cooldown With Steam Void in Vessel (Without RVLIS)".

While performing RCS depressurization steps in ES-0.4, which ONE of the following explains a function served by using the Pressurizer heaters to repressurize the RCS by 100 psig when Pressurizer level exceeds 90%?

A. Assists in cooling the upper head region of the vessel by collapsing the steam void.

B. Maintains Pressurizer conditions that allow restarting the Reactor Coolant Pumps when power is restored.

C. Provides exchange of liquid in the pressurizer to maintain Pressurizer and RCS boron concentrations within 50 ppm.

D. Ensures PZR liquid is at saturated conditions to limit the rate of pressure reduction when lowering PZR level.

Friday, March 04, 2016 10:17:05 AM 26

1603 NRC RO Exam

27. Given the following plant conditions:

- Unit 1 is operating at 100% power

- Subsequently, a small break LOCA occurs requring a Reactor trip and SI

- Current plant conditions require the crew to implement FR-P.1, "Pressurized Thermal Shock" While performing the steps of FR-P.1, after verifying adequate subcooling and RVLIS level, the crew is directed to establish normal charging to _______________.

A. allow use of auxiliary spray in the event the RCPs cannot be used during RCS depressurization.

B. reduce subsequent RVLIS minimum level requirements and thereby allow RCP restart to equalize system temperature.

C. eliminate ECCS flow as a source of RCS cooldown and to eliminate the possibility of SI causing a subsequent repressurization.

D. reduce unnecessary injection flow because subsequent minimum values for subcooling will be lower than normal SI termination criteria.

Friday, March 04, 2016 10:17:05 AM 27

1603 NRC RO Exam

28. Given the following plant conditions:

- Unit 1 is in Mode 3.

- RTBs are closed

- RCPs #2 & #3 are in operation

- USST 1A and USST 1B are out of service for corrective maintenance

- Maintenance presonnel are performing relay calibrations on the 1B Start Bus

- Subsequently, the 1B Start Bus trips out on differential relay actuation Which ONE of the following completes the statement below?

In accordance with Tech Spec 3.4.5, RCS Loops - Mode 3, _______ .

A. LCO met NO action(s) required B. the RTBs must be opened within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. at least 1 RCP must be restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D. immediately suspend any operation that would add positive reactivity Friday, March 04, 2016 10:17:05 AM 28

1603 NRC RO Exam

29. Given the following plant conditions:

- Unit 1 is in Mode 5 with the PZR solid.

- Train "A" RHR is aligned to provide shutdown cooling.

- An equipment malfunction occurs causing RCS pressure to rise.

- 1A-A RHR pump has just been tripped.

- It is reported that RCS pressure is 375 psig and rising.

In accordance with AOP-R.03, "RHR System Malfunctions," which ONE of the following identifies the RCS pressure at which FCV-74-1 & FCV-74-2, RHR Suction from Loop 4 hot leg, are closed and the reason for this action?

A. 380 psig, to prevent LTOP from initiating.

B. 410 psig, to ensure RCP seals are not damaged.

C. 450 psig, to prevent inventory loss through the suction relief valve.

D. 600 psig, to prevent over-pressurization of the PRT.

Friday, March 04, 2016 10:17:05 AM 29

1603 NRC RO Exam

30. Given the following plant conditions:

- Unit 2 was manually tripped and Safety Injection initiated from 100% power due to a Steam Generator Tube Rupture.

- Coincident with the reactor trip, all four (4) Unit 2 6.9KV Unit boards lock out.

- When attempting to de-pressurize the RCS, neither PZR PORV would open.

- The crew decides to use Auxiliary Spray to depressurize the RCS.

Which ONE of the following identifies the operational concern of using Auxiliary spray?

A. an additional loss of reactor coolant will occur.

B. excessive thermal stresses of spray nozzle may occur.

C. excessive thermal stresses of the PZR surge line will occur.

D. the rate of RCS pressure reduction will be difficult to control.

Friday, March 04, 2016 10:17:05 AM 30

1603 NRC RO Exam

31. Given the following plant conditions:

- Unit 1 is in solid plant operation

- 1A-A RHR pump is in service for shutdown cooling

- Charging and RHR letdown are in service

- The air line to Letdown Pressure Control Valve PCV-62-81 fails Which ONE of the following identifies how the plant will respond to this failure?

A. Charging flow will auto increase to maintain constant RCS pressure.

B. RCS pressure will increase until the Cold Overpressure Protection system actuates.

C. RCS pressure will decrease due to letdown line flow being greater than charging flow.

D. Train A RHR flow will increase resulting in RHR pump discharge relief valve lifting.

Friday, March 04, 2016 10:17:05 AM 31

1603 NRC RO Exam

32. Given the following plant conditions:

- Unit 1 is at 100% power.

- Subsequently, a LOCA has occurred.

- RCS pressure dropped rapidly to 1300 psig.

- While performing ES.05, "Equipment Verfications, step 11. Monitor ECCS operation," the following indications associated with 1B-B SI pump is observed:

- the "RED" indicating light on the pump control switch is LIT

- motor amps are at minimum

- flow is off-scale low

- discharge pressure is equal to that of 1A-A SI pump Based on the above indications, which ONE of the following completes the statement below?

The 1B-B SI pump indications __(1)__ expected and in accordance with ES-0.5, the operators are directed to __(2)__ .

A. (1) are (2) continue with ES-0.5 actions, no further action associated with SI pumps is required B. (1) are (2) ensure SI pump recirc valves FCV-1-63-3, FCV-1-63-4, and 1-63-175 are closed C. (1) are NOT (2) ensure SI pump valve alignment is correct before proceeding on in ES-0.5 D. (1) are NOT (2) close FCV-63-153, SI Pump B-B discharge crosstie before continuing on in ES-0.5.

Friday, March 04, 2016 10:17:05 AM 32

1603 NRC RO Exam

33. Given the following plant conditions:

- Unit 2 was manually tripped from 100% due to a small break LOCA

- A loss of Off-Site power occurred concurrently with the reactor trip

- Exosensor displays are not available

- The crew is performing ES-1.2, "Post LOCA Cooldown and Depressurization,"

Step 17, Depressurize RCS to establish PZR level greater than 20%

- Core Exit Temperature (auctioneered high core quadrant average) is 582°F

- All RCS Hot Leg Temperatures (Thot) are 562°F

- RCS average temperature (Tave) is 557°F

- RCS wide range pressure is 2200 psig

- Containment pressure is 1.0 psig Which ONE of the following identifies the approximate (+/- 5 psig) RCS pressure at which RCS subcooling may be lost (subcooling margin equals 0°F)?

A. 1347 psig B. 1332 psig C. 1167 psig D. 1120 psig Friday, March 04, 2016 10:17:05 AM 33

1603 NRC RO Exam

34. In accordance with 1-SO-68-5, "Pressurizer Relief Tank," which ONE of the following completes the statement below?

The maximum level allowed in the Pressurizer Relief Tank (PRT) before it is required to be drained is __(1)__ and the RCDT Pump B __(2)__ when 1-FCV-68-310, PRT Drain to RCDT, is opened.

A. (1) 64%

(2) auto-starts B. (1) 64%

(2) must be manually started C. (1) 88%

(2) auto-starts D. (1) 88%

(2) must be manually started Friday, March 04, 2016 10:17:05 AM 34

1603 NRC RO Exam

35. Given the following plant conditions:

- Both units are at 100% power.

- Spent Fuel Pool Cooling is aligned to Unit 2

- A spurious SI signal is generated on Unit 2 Which ONE of the following identifies the heat exchanger(s) that will lose Component Cooling System (CCS) cooling water?

A. The Spent Fuel Pool Cooling Heat Exchanger.

B. The Reactor Coolant Pump Seal (Leakoff) Water Heat Exchangers.

C. The CVCS Excess Letdown Heat Exchanger.

D. The Reactor Coolant Pump Thermal Barrier Heat Exchangers.

Friday, March 04, 2016 10:17:05 AM 35

1603 NRC RO Exam

36. Given the following plant conditions:

- Unit 1 is operating at 100% power

- Subsequently, a loss of off-site power occurs With NO operator action outside of the MCR, which pressurizer heaters are available to control RCS pressure?

A. Group A and Group C heaters will be automatically controlled.

B. Group C and Group D heaters can be manually controlled from M-4.

C. Group A and Group B heaters will be automatically controlled.

D. All heater groups can be manually controlled from M-4.

Friday, March 04, 2016 10:17:05 AM 36

1603 NRC RO Exam

37. Given the following plant conditions:

- Unit 1 is operating at 100% power.

- Channel 3 of the containment "HIGH-HIGH PRESS" pressure switches is out of service for surveillance testing with its bistable BYPASSED.

- The associated channel 3 "HIGH PRESS" bistable has been tripped as allowed by Tech. Specs.

- Subsequently, channel 2 of the containment "HIGH PRESS" pressure switch fails high such that a high pressure signal is initiated.

- Rx Trip and SI actuate.

Which ONE of the following describes the response of the Containment Spray System and the plant to the pressure switch failure?

A. Containment Spray will actuate; Cont. Isolation Phase A actuates.

B. Containment Spray will NOT actuate; Cont. Isolation Phase A actuates.

C. Containment Spray will actuate; Cont. Isolation Phase B actuates.

D. Containment Spray will NOT actuate; Cont. Isolation Phase B actuates.

Friday, March 04, 2016 10:17:05 AM 37

1603 NRC RO Exam

38. Given the following plant conditions:

- Unit 1 is initially at 100% power when an event occurred.

- The crew has just restored power to FCV-63-1, RHR pump suction from RWST, at step 6 of ES-1.3, "Transfer to RHR Containment Sump."

- RWST level is 20% and lowering.

- CNTMT pressure is 1.5 psig and lowering.

- Alarm: LS-63-176 CNTMT LEVEL HI RHR RECIRC (1-M6C-E4) is LIT

- 1-HS-63-72A, CNTMT Sump Suct To RHR Pump 1A, Red light LIT

- 1-HS-63-73A, CNTMT Sump Suct To RHR Pump 1B, Red light LIT

- 1-HS-72-39A, CNTMT Spray Hdr 1A Isol, Green light LIT

- 1-HS-72-2A, CNTMT Spray Hdr 1B Isol, Green light LIT Which ONE of the following completes the statement below?

Based on the above indications the RHR CNTMT Sump suction valves ____(1)____

in the expected positions and the CNTMT Spray Header isolations ___(2)___

in the expected positions.

A. (1) are (2) are B. (1) are (2) are NOT C. (1) are NOT (2) are D. (1) are NOT (2) are NOT Friday, March 04, 2016 10:17:05 AM 38

1603 NRC RO Exam

39. Given the following plant conditions:

- Unit 1 is at 100% power

- Subsequently, a Loss of Off-Site Power occurs

- A steam line break has generated a safety injection signal but Engineered Safety Feature Actuation System (ESFAS) Train "A" did NOT actuate

- Containment pressure indicates 2.9 psig and rising Assuming NO manual actions have been initiated, which ONE of the following identifies a consequence of that failure?

A. 1A-A MDAFW pump will remain in standby.

B. Only the B Train load sequencer will be operating.

C. Only two Main Steam Isolation Valves (MSIV's) will automatically close.

D. Only one Phase A Containment Isolation Valve in each penetration will automatically close.

Friday, March 04, 2016 10:17:05 AM 39

1603 NRC RO Exam

40. Given the following plant conditions:

- Unit 1 is operating at 100% power.

Which ONE of the following statements identifies both the maximum containment ice bed temperature allowed in accordance with 1-SI-OPS-000-002.0, "Shift Logs," and a potential effect of operating above the maximum temperature?

Maximum Temperature. Potential Effect A. 20°F Exceeding 12 psig inside Containment during a LOCA B. 20°F Exceeding 12 psig inside Containment during a Steam Line Break C. 27°F Exceeding 12 psig inside Containment during a LOCA D. 27°F Exceeding 12 psig inside Containment during a Steam Line Break Friday, March 04, 2016 10:17:05 AM 40

1603 NRC RO Exam

41. Given the following plant conditions:

- Unit 2 is operating at 100% power.

- Due to a loss of Lower Compartment Cooling, lower containment temperature has risen from 110°F to 119°F.

- Actions are in progress to restore cooling.

If the temperature continues to rise in containment, which ONE of the following describes the effect on pressurizer level indication?

The controlling pressurizer level channel will indicate slightly...

A. higher than actual level, and remain lower than the cold-calibrated pressurizer level instrument.

B. lower than actual level, and remain lower than the cold-calibrated pressurizer level instrument.

C. higher than actual level, and remain higher than the cold-calibrated pressurizer level instrument.

D. lower than actual level, and remain higher than the cold-calibrated pressurizer level instrument.

Friday, March 04, 2016 10:17:05 AM 41

1603 NRC RO Exam

42. Given the following plant conditions:

- Unit 1 at 100% power.

- An inadvertent Reactor Trip and Safety Injection occurred.

- Ice Condenser System glycol trapped between the inside and outside Containment penetration's return isolation valves expanded due to heating.

Which ONE of the following identifies the system response to the glycol expansion?

A. The penetration's inside glycol isolation valve disks are designed to relieve trapped glycol into the Containment side glycol supply header.

B. The penetration's outside glycol isolation valve disks are designed to relieve trapped glycol into the Auxiliary Building side glycol supply header.

C. A bypass line with a check valve is installed around the penetration's inside isolation valve to relieve trapped glycol into the Containment side glycol supply header.

D. A relief valve is installed between the penetration's inside and outside isolation valves to relieve trapped glycol into the Containment.

Friday, March 04, 2016 10:17:05 AM 42

1603 NRC RO Exam

43. Given the following plant conditions:

- Unit 1 tripped from 100% power due to a LOCA.

- The crew is implementing ES-1.3, "Transfer to RHR Containment Sump,"

and preparing to align the suction of the Containment Spray pumps to the containment sump.

Which ONE of the following identifies an INTERLOCK associated with containment sump level which must be satisfied before 1-FCV-72-23, Containment Spray Pump 1A Suction from Containment Sump will open?

Containment sump level must be at least _____ .

A. 8%

B. 11%

C. 18%

D. 56%

Friday, March 04, 2016 10:17:05 AM 43

1603 NRC RO Exam

44. Given the following plant conditions:

- Unit 1 is in Mode 4 with RCS temperature at 310°F during a plant heatup.

- The MSIV bypass valves are open to warm the Main Steam Lines.

- Differential pressure across the MSIVs is 30 psid.

- The operating crew is planning to open the MSIVs when the steamline deltaP criteria is met.

Which ONE of the following completes the statements below?

In accordance with 1-SO-1-1, "Main Steam System," the maximum pressure differential allowed across an MSIV to allow it to be opened is ___(1)___ and SRO permission ___(2)___ required to open the MSIV at this pressure.

___(1)___ ___(2)___

A. 15 psid is NOT B. 15 psid is C. 25 psid is NOT D. 25 psid is Friday, March 04, 2016 10:17:05 AM 44

1603 NRC RO Exam

45. Given the following plant conditions:

- Unit 2 is in Mode 3

- RCS pressure is 2235 psig

- Tavg is being maintained by the steam dumps in Steam Pressure mode at 1005 psig.

- Atmospheric relief valve controllers have been set per 2-SO-1-1, "Main Steam System."

- All four RCP's are running.

- Subsequently, a complete loss of Condenser vacuum occurs.

Which ONE of the following identifies the value at which RCS Tavg is expected to stabilize? (Assume NO operator action) o A. 547 F B. 549oF C. 552oF D. 554oF Friday, March 04, 2016 10:17:05 AM 45

1603 NRC RO Exam

46. Given the following plant conditions:

- Unit 1 is in Mode 2 performing a plant startup.

- Breaker 523 "MFPT A 250V DC Trip" bus supply breaker is OPEN.

- Breaker 524 "MFPT B 250V DC Trip" bus supply breaker is CLOSED.

- The "B" MFWP turbine is RESET and NOT pumping forward.

- Subsequently, injection water supply pressure drops to <220 psig for 25 seconds before returning to normal.

Which ONE of the following completes the statements below?

The "B" MFWP __(1)__ auto trip.

and the AFW pumps __(2)__ receive an auto start signal.

A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT Friday, March 04, 2016 10:17:05 AM 46

1603 NRC RO Exam

47. Given the following conditions:

- Unit 2 is operating at 100% power.

- Subsequently, instrument failures cause a spurious Main Feedwater Isolation Signal.

- NO Auxiliary Feedwater Pumps start.

- The reactor does NOT trip.

- AMSAC fails to actuate.

Assuming NO operator action, which ONE of the following is the primary concern and why?

A. Loss of RCS integrity caused by an overpressure transient.

B. Main steamline break caused by thermal shock on Steam Generator shell.

C. SG tube rupture caused by high primary-to-secondary differential pressure.

D. Overpower condition caused by the failure of the turbine to receive a trip signal.

Friday, March 04, 2016 10:17:05 AM 47

1603 NRC RO Exam

48. Given the following plant conditions:

- Unit 1 is operating at 100% power

- During the performance of a surveillance test on the TDAFW pump, the following alarm is received:

AUX FWP TURBINE 1A-S MECHANICAL OVERSPEED TRIP (1-M-3C, A-4)

- The cause of the alarm is determined to be 1-FIC-46-57 failed to control the pump outlet flow.

Which ONE of the following identifies:

(1) the setpoint for this alarm AND (2) after the Mechnical Overspeed mechanism is RESET and LATCHED, the action required prior to attempting to restart the TDAFW pump in accordance with 1-SO-3-2, "Auxiliary Feedwater System?

A. (1) 4300 rpm (2) Hold 1-HS-1-51A-S, Trip/Throttle Valve, closed for 10 seconds to clear the overspeed alarm, then open Trip/Throttle valve using 1-HS-51-A-S.

B. (1) 4300 rpm (2) Place speed controller in MANUAL and set controller output at 20%, then open Trip/Throttle valve using 1-HS-1-51A-S.

C. (1) 4900 rpm (2) Hold 1-HS-1-51A-S, Trip/Throttle Valve, closed for 10 seconds to clear the overspeed alarm, then open Trip/Throttle valve using 1-HS-51-A-S.

D. (1) 4900 rpm (2) Place speed controller in MANUAL and set controller output at 20%, then open Trip/Throttle valve using 1-HS-1-51A-S.

Friday, March 04, 2016 10:17:05 AM 48

1603 NRC RO Exam

49. Given the following plant conditions:

- Both units are at 100% power.

- The following annunciator was received on Unit 1:

"120V AC VITAL INVERTER 1-I OR INVERTER 0-I ABNORMAL" (1M-C, A6)

- AUOs were dispatched to the inverters and found the yellow "BYPASS SOURCE SUPPLYING LOAD" light lit on the inverter 1-I.

Which ONE of the following completes the statements below?

The inverter has transferred to the __(1)__ .

and LCO 3.8.7 "Inverters - Operating" __(2)__ be entered.

A. (1) 125V DC Vital Battery Board (2) would B. (1) 125V DC Vital Battery Board (2) would NOT C. (1) Isolimiter (Reg) transformer (2) would D. (1) Isolimiter (Reg) transformer (2) would NOT Friday, March 04, 2016 10:17:05 AM 49

1603 NRC RO Exam

50. Which ONE of the following would indicate that the 125V DC Vital Battery Charger 1 output breaker tripped open?

Panel 1M-C annunciator __(1)__ would alarm and indicator EI-57-92, Batt BD I AMPS, would be indicating __(2)__ from zero.

A. (1) "125V DC VITAL BAT BD I ABNORMAL" (A-5)

(2) upscale B. (1) "125V DC VITAL BAT BD I ABNORMAL" (A-5)

(2) downscale C. (1) "125 V DC VITAL CHGR I FAILURE OR VITAL BAT I DISCHARGE" (A-4)

(2) upscale D. (1) "125 V DC VITAL CHGR I FAILURE OR VITAL BAT I DISCHARGE" (A-4)

(2) downscale Friday, March 04, 2016 10:17:05 AM 50

1603 NRC RO Exam

51. Given the following plant conditions:

- The Diesel Generator 1A-A Day Tank Fuel Oil Transfer Pump #1 is running in automatic due to a low level in a 1A-A Day Tank caused when maintenance pumped out the day tank .

- The D/G 1A-A is NOT running at this time.

- Subsequently, 6.9Kv Unit Bd 1B trips on a ground fault.

Which ONE of the following completes the statement below?

The Diesel Generator Day Tank Fuel Oil Transfer Pump will .....

A. continue to run since it is DC powered from the D/G battery.

B. continue to run since it is powered from "B" train shutdown power.

C. stop and require manual restart after 6.9 kv Shutdown Bd 1A-A is energized.

D. stop and after the 1A-A D/G ties onto the 1A-A 6.9 kv Shutdown Bd., the pump will restart.

Friday, March 04, 2016 10:17:05 AM 51

1603 NRC RO Exam

52. Given the following plant conditions:

- Unit 1 is operating at 100% power

- Total primary to secondary leakage is 70 gpd

- Identified RCS leakage is 0.18 gpm

- Unidentified RCS leakage is 0.2 gpm

- Pzr level, VCT level, charging flow, and letdown flow are all stable Which ONE of the following conditions would provide the first indications in the control room of a developing fuel element defect?

A. Annunciator "1-RA-272A UPPR IN CNTMT HI RAD" alarms and a rapidly increasing count rate on 1-RM-90-112A/B/C "Upper Containment Air Monitor."

B. A slowly increasing count rate on 1-RM-90-119 "Condenser Vacuum Exhaust Monitor" and NO increase in count rate on 1-RM-90-106A/B "Lower Containment Air Monitor."

C. A slowly increasing count rate on 1-RM-90-130A and -131A "Containment Purge Exhaust Monitors" and Annunciator "1-RA-272A UPPR IN CNTMT HI RAD" alarms.

D. A slowly increasing count rate on 1-RM-90-106A/B "Lower Containment Air Monitor" and a slowly increasing count rate on 1-RM-90-119 "Condenser Vacuum Exhaust Monitor."

Friday, March 04, 2016 10:17:05 AM 52

1603 NRC RO Exam

53. Given the following plant conditions:

- Both Units operating at 100% power

- All systems aligned normally If a large ERCW leak developed at the inlet to the 1A1 CCS Heat Exchanger, which ONE of the ERCW Headers would have increased flow, and when the leak was isolated, how would the 1A and 2A ERCW header pressures be effected?

Header with Effect on Header Pressure Flow Increase after leak is isolated A. 1A Both 1A and 2A header pressures would increase B. 1A Only the 1A header pressure would increase C. 2A Both 1A and 2A header pressures would increase D. 2A Only the 2A header pressure would increase Friday, March 04, 2016 10:17:05 AM 53

1603 NRC RO Exam

54. Given the following plant conditions:

- Unit 1 is in Mode 5 with 6.9kV Shutdown Board 1A-A tagged for maintenance.

- Subsequently, 6.9kV Shutdown Board 2B-B trips and locks out due to relay operation.

Which ONE of the following identifies the status of the Auxiliary Air Compressor power supplies?

A. Both Auxiliary Air Compressors have a power supply available.

B. Neither Auxiliary Air Compressor has a power supply available.

C. Only the Auxiliary Air Compressor A-A has a power supply available.

D. Only the Auxiliary Air Compressor B-B has a power supply available.

Friday, March 04, 2016 10:17:06 AM 54

1603 NRC RO Exam

55. Given the following plant conditions:

- Unit 2 experienced a manual Safety Injection (SI).

- Containment Purge Rad Monitor, 2-RM-90-130, was in high rad alarm but has been reset.

- Containment Purge Rad Monitor, 2-RM-90-131, indicates normal.

- Containment Vent Isolation occurred on Train A.

- Containment Vent Isolation did NOT occur on Train B.

- Phase A has been RESET.

- SI signal has NOT been RESET.

Which ONE of the following identifies the status of the Containment Vent Isolation (CVI) system?

The CVI ____________________ and __________________________.

A. should have occurred on A and B Train; the CVI can be reset with the SI signal present.

B. should have occurred on A and B Train; the SI signal must be reset before the CVI can be reset.

C. should NOT have occurred on B Train; the CVI can be reset with the SI signal present.

D. should NOT have occurred on B Train; the SI signal must be reset before the CVI can be reset.

Friday, March 04, 2016 10:17:06 AM 55

1603 NRC RO Exam

56. Given the following plant conditions:

- Unit 2 is at 100% power.

- Subsequently, a Reactor trip and SI have actuated.

- RCS pressure is 300 psig and LOWERING.

- PZR level is offscale LOW.

- RCS temperature is 504°F and LOWERING.

- Containment pressure is 6 psig and RISING slowly.

- S/G pressures are 690 psig and LOWERING slowly.

- Crew is performing E-0, "Reactor Trip or Safety Injection".

Which ONE of the following identifies the cause of these conditions?

A. RCS Cold Leg Break.

B. PZR Safety Valve failed OPEN.

C. Main Feed Line Break inside containment.

D. Main Steam Line Break inside containment.

Friday, March 04, 2016 10:17:06 AM 56

1603 NRC RO Exam

57. Which ONE of the following identifies all nuclear instruments that are powered from 120V AC Vital Instrument Power Board 1-I?

A. N-31 and N-41 only B. N-35 and N-41 only C. N-31 and N-35 only D. N-31, N-35, and N-41 Friday, March 04, 2016 10:17:06 AM 57

1603 NRC RO Exam

58. GIven the following plant conditions:

- Unit 1 is at 100% power

- Subsequently, a small break LOCA has occurred.

- Core exit thermocouples (T/C) are being monitored by the STA.

In accordance with GOI-6, "Apparatus Operations," which ONE of the following identifies both the indication range and the display code which indicates that a Core Exit Thermocouple is out of electrical limits?

Indication Range Code for out of electrical limits A. 200 - 2300 F "XXX "

B. 200 - 2300 F " ? " (question mark)

C. 0 - 3000 F " ? " (question mark)

D. 0 - 3000 F " XXX "

Friday, March 04, 2016 10:17:06 AM 58

1603 NRC RO Exam

59. Given the following plant conditions:

- Unit 1 has experienced a Large break LOCA.

- FR-C.1,"Inadequate Core Cooling," is being implemented.

- Containment pressure is 10 psig and slowly lowering.

- Containment hydrogen concentration is 6.5% and slowly rising.

Which ONE of following identifies the Hydrogen Recombiner operation?

Hydrogen recombiner operation....

A. is not allowed because of the operation of containment spray.

B. is allowed provided the hydrogen igniters have previously been placed in service.

C. is allowed, however the maximum power setting is limited.

D. is not allowed because it may cause a sudden rise in containment pressure.

Friday, March 04, 2016 10:17:06 AM 59

1603 NRC RO Exam

60. Given the following plant conditions:

- Unit 1 core has been off-loaded.

- Irradiated fuel shuffles are in progress in the spent fuel pool.

- Main Control Room Radiation Monitor, 0-RM-90-125, fails due to an instrument malfunction.

Which ONE of the following identifies if the radiation monitor failure would require an LCO entry on Unit 1 and the effect the failure would have on the movement of irradiated fuel in the spent fuel pit?

LCO Condition entry Fuel Movement A. Required Can continue B. Required Must be stopped C. NOT required Can continue D. NOT required Must be stopped Friday, March 04, 2016 10:17:06 AM 60

1603 NRC RO Exam

61. Given the following plant conditions:

- Unit 1 is at 100% power.

- A reactor trip is initiated by operator action.

- RTB "B" does NOT open on the trip.

Which ONE of the following identifies the expected response of the steam dump system?

The steam dumps will attempt to maintain the RCS Tavg at __(1)__ with the

__(2)__ controller.

A. (1) 547°F (2) reactor trip B. (1) 547°F (2) load rejection C. (1) 552°F (2) reactor trip D. (1) 552°F (2) load rejection Friday, March 04, 2016 10:17:06 AM 61

1603 NRC RO Exam

62. Which ONE of the following identifes:

(a) how main steam header pressure will respond as turbine load is raised from 50%

to 70%

and (b) the method of maintaining Tavg on program which would result in the value for MTC being the MOST negative as turbine load was raised?

A. (a) header pressure will lower (b) maintain rod position constant, while lowering Boron concentration to maintain Tavg on program B. (a) header pressure will lower (b) withdraw control rods to maintain Tavg on program, while holding Boron concentration constant C. (a) header pressure will rise (b) maintain rod position constant, while lowering Boron concentration to maintain Tavg on program D. (a) header pressure will rise (b) withdraw control rods to maintain Tavg on program, while holding Boron concentration constant Friday, March 04, 2016 10:17:06 AM 62

1603 NRC RO Exam

63. Given the following plant conditions;

- Unit 1 is operating at 100% power when CBP 1A trips.

- The operating crew enters AOP-S.04, "Condensate or Heater Drains Malfunction."

- Investigation determines the pump to be damaged and will be out of service for several days.

Which ONE of the following completes the statements below in accordance with AOP-S.04?

An immediate load reduction may be required to maintain MFP suction pressures greater than a minimum of __(1)__ psig.

With the pump being out of service for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the procedure directs an evaluation of a power reduction to at least less than __(2)__ to reduce the risk of a unit trip if any additional secondary plant malfunctions occurs.

(1) (2)

A. 250 85%

B. 250 75%

C. 320 85%

D. 320 75%

Friday, March 04, 2016 10:17:06 AM 63

1603 NRC RO Exam

64. Given the following plant conditions:

- Both Units are operating at 100% power.

- 0-RM-90-103A, Spent Fuel Pit Radiation Monitor, fails HIGH.

Which ONE of the following indentifies the expected plant response?

A. ONLY Train B Aux Building Isolation dampers close; ONLY Train B Aux Building General Supply, Exhaust and Fuel Handling exhaust fans trip.

B. ONLY Train B Aux Building Isolation dampers close; ALL Aux Building General Supply, Exhaust and Fuel Handling exhaust fans trip.

C. ONLY Train A Aux Building Isolation dampers close; ONLY Train A Aux Building General Supply, Exhaust and Fuel handling exhaust fans trip.

D. BOTH Train A and Train B Aux Building Isolation dampers close; ALL Aux Building General Supply, Exhaust, and Fuel handling exhaust fans trip.

Friday, March 04, 2016 10:17:06 AM 64

1603 NRC RO Exam

65. Given the following plant conditions:

- Maintenance personnel report that a Service Air connection providing air to a pneumatic grinder has broken and cannot be isolated.

- Air Header Pressure indications are as follows:

PI-32-104A, AUX CONT AIR HDR A PRESS 92 psig PI-32-105A, AUX CONT AIR HDR B PRESS 92 psig PI-32-200, CONT AIR HDR PRESS 94 psig and slowly lowering PI-33-199, SERV AIR HDR PRESS 90 psig and slowly lowering Which ONE of the following completes the statements below?

(1) At the current pressures, PCV-33-4, SERVICE AIR ISOL ___(1)__ open.

(2) If PCV-33-4 automatically closes, once the Service Air Header is repressurized, the valve ___(2)___ .

A. (1) is (2) must be reset before it will open B. (1) is (2) will reopen automatically C. (1) is NOT (2) must be reset before it will open D. (1) is NOT (2) will reopen automatically Friday, March 04, 2016 10:17:06 AM 65

1603 NRC RO Exam

66. Which ONE of the following completes the statement below?

Concerning the operation of the Steam Dump Control System, when the "D" solenoids are energized they ____ .

A. allow the steam dump valves to respond more quickly when needed B. prevent the steam dump valves from opening if the condenser is not available C. align control air to supply for modulation control when the steam dumps are armed D. allow the steam dump cooldown valves to open when Tavg is below the Lo-Lo Tavg interlock Friday, March 04, 2016 10:17:06 AM 66

1603 NRC RO Exam

67. Which ONE of the following identifies the alternate locations available for charging flow control and indication outside of the Main Control Room?

Aux Control Room Locally in the Aux Building (1-L-10) (1-L-112A)

A. Controller functions and the flow No control function on panel, indication reads only with Nor-Aux flow indication only switch in AUX B. Controller functions and the flow Panel has both controller indication reads only with Nor-Aux function and flow indication switch in AUX C. Controller functions only with No control function on panel, Nor-Aux switch in AUX flow indication only Indication reads with Nor-Aux switch in either position D. Controller functions only with Panel has both controller Nor-Aux switch in AUX function and flow indication Indication reads with Nor-Aux switch in either position Friday, March 04, 2016 10:17:06 AM 67

1603 NRC RO Exam

68. Given the following plant conditions:

- Unit 1 is preparing for a startup with the RCS at 540°F.

Which ONE of the following completes the statements below?

The value for Safety Limit 2.1.2, "RCS Pressure SL" is ___(1)___.

AND Violation of SL 2.1.2 requires RCS pressure to be reduced to less than the limit within ___(2)___ from the time the limit was violated.

___(1)___ ___(2)___

A. 2485 psig 5 minutes B. 2485 psig 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. 2735 psig 5 minutes D. 2735 psig 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Friday, March 04, 2016 10:17:06 AM 68

1603 NRC RO Exam

69. Given the following plant conditions:

- A main control room annunciator, 2-M15-A, A-4, PdS-27-13B TRAV SCREEN 2B DIFF PRESS HI, has alarmed repeatedly over the past hour.

- Traveling Screen delta P on 2-PDI-27-13A reads 1.5 in. H20 and steady.

- An AUO is dispatched to CCW pumping station several times and reports:

- local screen delta P reads 1.5 in. H2O

- there are NO visible obstructions

- Screen wash pumps and traveling screens are NOT running Based on the given conditions, which ONE of the following completes the statements below?

In accordance with OPDP-4, "Annunciator Disablement," this alarm __(1)__ the definition of a nuisance alarm.

and Any annuciator that is disabled due to being a nuisance alarm, ___(2)___

required to be logged in the narrative log.

A. (1) meets (2) is B. (1) meets (2) is NOT C. (1) does NOT meet (2) is D. (1) does NOT meet (2) is NOT Friday, March 04, 2016 10:17:06 AM 69

1603 NRC RO Exam

70. Which ONE of the following completes the statement below?

A SQN plant worker has lifetime accumulated dose of 900 mrem as documented on an NRC form 4.

In accordance with NPG-SPP-5.1, "Radiological Controls," the worker's yearly administrative whole body dose limit is __(1)__ and to exceed the administrative dose limit __(2)__ approval is required.

A. (1) .5 Rem TEDE (2) Rad Protection Manager B. (1) .5 Rem TEDE (2) Shift Manager C. (1) 1 Rem TEDE (2) Rad Protection Manager D. (1) 1 Rem TEDE (2) Shift Manager Friday, March 04, 2016 10:17:06 AM 70

1603 NRC RO Exam

71. A Monitor Tank release is in progress.

- 0-RCV-77-43, Liquid Radwaste Release Valve, closed to terminate the release.

Which ONE of the following identifies the conditions that would directly cause a Monitor Tank release to automatically terminate?

I. Less than 2 ERCW pumps per train running II. Loss of power to 0-RCV-77-43, Liquid Radwaste Release Valve III. 0-RM-90-122, Liquid Radwaste Release Monitor low flow (< 2.5 gpm)

A. II ONLY B. II and III ONLY C. I and II ONLY D. I, II, and III Based on a question during the exam: How many pumps are running in each train.

The applicants were informed that 2A and 1B ERCW pumps are running.

Friday, March 04, 2016 10:17:06 AM 71

1603 NRC RO Exam

72. Prior to an entry into lower containment being made, which ONE of the following identifies the verifications that are required relative to the incore flux detector placement and tagging?

Detector Placement Tagged with a...

A. Storage position, only Caution Order B. Storage position, only Hold Order C. Storage position or inserted Caution Order to within 10 feet of the core D. Storage position or inserted Hold Order to within 10 feet of the core Friday, March 04, 2016 10:17:06 AM 72

1603 NRC RO Exam

73. Which ONE of the following sets of plant paramaters will result in a RED path on the Heat Sink Status Tree?

A. Containment Pressure is 2 psig S/G 1 S/G 2 S/G 3 S/G 4 NR Level 40% 15% 28% 28%

WR Level ---- ---- ---- ----

AFW Flow 60gpm 130 gpm 80 gpm 50 gpm B. Containment Pressure is 2 psig S/G 1 S/G 2 S/G 3 S/G 4 NR Level ---- ---- 5% 8%

WR Level 0% 0% ---- ----

AFW Flow 0 gpm 0 gpm 190 gpm 255 gpm C. Containment Pressure is 3 psig S/G 1 S/G 2 S/G 3 S/G 4 NR Level ---- ---- 24% 23%

WR Level 20% 20% ---- ----

AFW Flow 100 gpm 100 gpm 100 gpm 100 gpm D. Containment Pressure is 3 psig S/G 1 S/G 2 S/G 3 S/G 4 NR Level ---- 22% 21% 23%

WR Level 0% ---- ---- ----

AFW Flow 0 gpm 160 gpm 155 gpm 140 gpm Friday, March 04, 2016 10:17:06 AM 73

1603 NRC RO Exam

74. Which ONE of the following identifies...

(1) the Emergency Response Organization responsible for dispatching Emergency Response Teams during a plant emergency and (2) the lowest level emergency that will result in the emergency center being required to be staffed?

(1) (2)

A. Technical Support Center Alert B. Technical Support Center SAE C. Operations Support Center Alert D. Operations Support Center SAE Friday, March 04, 2016 10:17:06 AM 74

1603 NRC RO Exam

75. Given the following plant condtions:

- Unit 1 is shutting down and is currently 230°F

- 1A RHR train is being placed in service per 0-SO-74-1, "Residual Heat Removal System."

- RHR Letdown has been placed in service at maximum flow.

- CCS flow thru the 1A-A RHR heat exchanger is 1000 gpm.

- FCV-63-93, RHR Pump A-A Discharge to Loops 2 and 3 Cold Leg, has just been opened.

- Annunciator "RHR HX A OUTLET TEMPERATURE HIGH," (0-M27-B-A, E-6) alarms.

Which ONE of the following identifies the valve leaking by that will result in the alarm and the operator action to mitigate in accordance with the Annunciator Response?

Condition Action to mitigate A. FCV-74-16, RHR Hx 1A Outlet Remove RHR Letdown from service.

Flow Control Valve B. FCV-74-32, RHR Hx 1A and 1B Remove RHR Letdown from service.

Bypass Flow Control Valve C. FCV-74-16, RHR Hx 1A Outlet Increase CCS flow through the 1A-A RHR Flow Control Valve Heat Exchanger.

D. FCV-74-32, RHR Hx 1A and 1B Increase CCS flow through the 1A-A RHR Bypass Flow Control Valve Heat Exchanger.

You have completed the test!

Friday, March 04, 2016 10:17:06 AM 75

ANSWER KEY REPORT for 1603 NRC RO Exam Test Form: 0 Answers

ID Points Type 0 1 007 EK2.03 501 1.00 MCS B 2 009 EK.2.03 502 1.00 MCS B 3 015 AK3.03 503 1.00 MCS C 4 022 AG2.2.4 104 1.00 MCS B 5 025 AK1.01 505 1.00 MCS C 6 026 AA2.01 506 1.00 MCS C 7 027 AG2.1.7 107 1.00 MCS A 8 029 EK2.06 8 1.00 MCS A 9 054 AA1.04 9 1.00 MCS C 10 055 EA1.07 510 1.00 MCS A 11 057 AA2.20 311 1.00 MCS C 12 058 AA1.02 12 1.00 MCS B 13 062 AG2.4.47 13 1.00 MCS C 14 065 AA2.07 514 1.00 MCS C 15 W/E04 EK1.2 215 1.00 MCS B 16 W/E11 EK3.2 16 1.00 MCS A 17 W/E05 EK1.1 517 1.00 MCS C 18 077 AK3.01 18 1.00 MCS D 19 024 AG2.1.31 19 1.00 MCS B 20 028 AK1.01 520 1.00 MCS C 21 036 AK1.02 121 1.00 MCS A 22 037 AA2.12 22 1.00 MCS A 23 069 AK2.03 223 1.00 MCS C 24 068 AA1.12 124 1.00 MCS D 25 076 AK3.06 325 1.00 MCS B 26 W/E10 EG2.4.20 526 1.00 MCS A 27 W/E08 EK3.4 27 1.00 MCS C 28 003 G2.2.36 528 1.00 MCS B 29 004 K6.27 529 1.00 MCS C 30 004 K5.09 30 1.00 MCS B 31 005 K5.05 31 1.00 MCS C 32 006 A2.05 532 1.00 MCS C 33 006 K6.18 33 1.00 MCS B 34 007 A1.01 534 1.00 MCS C 35 008 A3.08 35 1.00 MCS C 36 010 K2.01 36 1.00 MCS C 37 012 K1.05 237 1.00 MCS B 38 013 A4.01 538 1.00 MCS A 39 013 K3.03 39 1.00 MCS D 40 025 K5.01 40 1.00 MCS C 41 022 K3.02 41 1.00 MCS C 42 025 K4.02 542 1.00 MCS C 43 026 K4.07 543 1.00 MCS B 44 039 K1.01 44 1.00 MCS D 45 039 K4.02 545 1.00 MCS B 46 059 G2.1.32 546 1.00 MCS B 47 061 K3.01 547 1.00 MCS A Friday, March 04, 2016 10:20:11 AM 1

ANSWER KEY REPORT for 1603 NRC RO Exam Test Form: 0 Answers

ID Points Type 0 48 061 K6.01 48 1.00 MCS D 49 062 A3.04 49 1.00 MCS C 50 063 A4.01 550 1.00 MCS C 51 064 K2.02 551 1.00 MCS D 52 073 A1.01 52 1.00 MCS D 53 076 A2.01 53 1.00 MCS C 54 078 K2.02 54 1.00 MCS C 55 103 A3.01 55 1.00 MCS A 56 002 K3.03 556 1.00 MCS A 57 015 K2.01 57 1.00 MCS D 58 017 K1.01 258 1.00 MCS B 59 028 A1.02 59 1.00 MCS D 60 034 G2.4.31 60 1.00 MCS A 61 041 K6.02 61 1.00 MCS B 62 045 K5.23 162 1.00 MCS A 63 056 A2.04 63 1.00 MCS C 64 072 A3.01 564 1.00 MCS B 65 079 K4.01 65 1.00 MCS A 66 G 2.1.28 166 1.00 MCS A 67 G 2.1.30 67 1.00 MCS D 68 G 2.2.39 568 1.00 MCS C 69 G 2.2.43 69 1.00 MCS A 70 G 2.3.4 170 1.00 MCS C 71 G 2.3.11 571 1.00 MCS B 72 G 2.3.12 72 1.00 MCS D 73 G 2.4.21 173 1.00 MCS C 74 G 2.4.29 174 1.00 MCS C 75 G 2.4.46 75 1.00 MCS C SECTION 1 ( 75 items) 75.00 Friday, March 04, 2016 10:20:11 AM 2

References for 1603 NRC RD Exam

1. Steam Tables

2. Mollier Diagram

3. TRM figure 8.1.1-4

4. O-GO-15, Appendix U, rev 40

5. AOP-M.01, pages7&8rev28

ES4OI Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: Facility/Unit: Sequoyah Station Units I & 2 Region: i II X Ill IV ReactorType:WXCEEIBWEIGEEI Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after the examination begins.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicants Signature Results Examination Value Points Applicants Score Points Applicants Grade Percent Q]

cktce,C iS ,,2 B Cc-w

Name: ________________________________ 1603 NRC RO Exam Form: 0 Version: 0

1. Given the following plant conditions:

- Unit 2 was at 60% power when a reactor trip occurred.

- After the crew has completed the immediate actions of E-0, "Reactor Trip or Safety Injection," the OATC observed the following on Annunciator Panel 2-XA-55-4D, "Reactor First Out":

- LS-3-97B, "STM GEN LOOP 3 LEVEL LOW-LOW REACTOR TRIP" window lit and NOT flashing.

- "P-9 TURBINE TRIP REACTOR TRIP" window flashing.

Which ONE of the following identifies the cause of the reactor trip and the status of the Reactor Trip First Out Panel?

A. The reactor tripped due to the turbine trip; The Reactor Trip First Out panel has been acknowledged, but NOT reset.

B. The reactor tripped due to the turbine trip; The Reactor Trip First Out panel has NOT been acknowledged and the SG Low-Low level window came in after the reactor trip occurred.

C. The reactor tripped due to the SG low level; The Reactor Trip First Out panel has been acknowledged, but NOT reset.

D. The reactor tripped due to the SG low level; The Reactor Trip First Out panel has been acknowledged and the P-9 Turbine Trip Reactor Trip window came in after the panel was acknowledged.

Friday, March 04, 2016 10:17:05 AM 1

1603 NRC RO Exam

2. Given the following plant conditions:

- Unit 2 is manually tripped from 100% power due to rapidly lowering PZR level and pressure.

- The crew has entered E-1, "Loss of Reactor or Secondary Coolant"

- The crew is directed to MAINTAIN Intact S/G narrow range levels.

Which ONE of the following completes the statement below?

S/G level is required for __(1)__ events because heat removal by S/Gs __(2)__.

A. (1) SBLOCA (2) ensures no core uncovery occurs B. (1) SBLOCA (2) is needed during recovery to achieve Cold Shutdown C. (1) LBLOCA (2) ensures core exit TCs do not exceed 700°F D. (1) LBLOCA (2) is needed during recovery to achieve Cold Shutdown Friday, March 04, 2016 10:17:05 AM 2

1603 NRC RO Exam

3. Given the following plant conditions:

- Unit 1 is operating at 100% power

- Main Feed Reg valve for #2 SG fails closed

- Subsequently an automatic reactor trip signal is generated

- An ATWS is in progress

- Reactor power is at 9% and lowering

- #2 RCP Lower Motor Bearing temp is 285°F and rising rapidly.

In accordance with FR-S.1, "Nuclear Power Generation/ATWS," which ONE of the following identifies when #2 RCP can be tripped and what is the basis?

A. immediately to conserve secondary inventory B. Immediately to protect the pump for later use C. wait until below 5% reactor power to prevent fuel integrity challenge D. wait until below 5% reactor power to allow SG level to be recovered prior to securing pump.

Friday, March 04, 2016 10:17:05 AM 3

1603 NRC RO Exam

4. Given the following plant conditions:

- Both Units are at 100% power

- The "B" BAT has been removed from service due to a leak

- The "C" BAT is being placed in service on Unit 2.

- The RWST boron concentration is 2600 ppm.

Which ONE of the following identifies both:

(1) the minimum allowable "C" BAT volume and boron concentration required by TRM 8.1.1 "Boration Systems - Operating,"

and (2) the location that BAT "C" level indicator 0-LI-62-242, can be read?

REFERENCE PROVIDED A. (1) 9250 gals at 6650 ppm Boron (2) 1-M-6 ONLY B. (1) 9500 gals at 6600 ppm Boron (2) 1-M-6 ONLY C. (1) 9250 gals at 6650 ppm Boron (2) 1-M-6 and 2-M-6 D. (1) 9500 gals at 6600 ppm Boron (2) 1-M-6 and 2-M-6 Friday, March 04, 2016 10:17:05 AM 4

1603 NRC RO Exam

5. Given the following plant conditions:

- Unit 2 is in Mode 6.

- RCS drained to elevation 701 feet.

- RCS temperature is 110°F.

- Upper Internals are not installed.

- Core decay heat is approximately 5 MW.

- A total loss of RHR cooling has occurred.

Which ONE of the following identifies the minimum amount of time it will take to reach 212°F in the RCS?

Reference Provided A. 30 minutes B. 36 minutes C. 49 minutes D. 347 minutes Friday, March 04, 2016 10:17:05 AM 5

1603 NRC RO Exam

6. Given the following plant conditions:

- Unit 1 is in Mode 3 for maintenance.

- An event occurs which results in all of the following annunciators:

- "MISC EQUIP SUPPLY HEADER FLOW LOW," (M27B-B, A-3).

- "LETDOWN HX OUTLET FLOW/TEMP ABNORMAL," (M27B-B, A-5)

- "TS-62-78 LTDN HX OUTLET TO DEMIN TEMP HIGH," (M6C, A4)

- "TURB AUX OR REAC BLDG FLOODED" (M15B, D3)

Which ONE of the following identifies the cause of these alarms?

A leak on the ____ .

A. charging header B. letdown line C. "A" train of CCS D. ERCW header Friday, March 04, 2016 10:17:05 AM 6

1603 NRC RO Exam

7. Given the following plant conditions:

- Unit 2 is operating at 100% power.

- A failure of the controlling input to the Pressurizer Pressure Master Controller caused actual pressurizer pressure to increase to 2273 psig.

- The Pressurizer Pressure Master Controller, PIC-68-340A, has been placed in MANUAL.

Which ONE of the following describes the action required to return pressure to 2235 psig?

A. Raise the master controller output B. Lower the master controller output C. Raise the master controller pressure setpoint D. Lower the master controller pressure setpoint Friday, March 04, 2016 10:17:05 AM 7

1603 NRC RO Exam

8. Given the following plant conditions:

- Unit 1 is at 100% power

- SSPS testing in progress

- RTA and BYB Reactor Trip Breakers are shut

- Reactor Trip Breaker "B" is open

- Subsequently, a transient occurs that requires a reactor trip but the reactor fails to trip from the trip switch.

Which ONE of the following completes the statements below?

The RTA & BYB 125V dc trip coils failed to __(1)__ .

If only BYB is opened locally, the reactor __(2)__ trip.

A. (1) energize (2) will B. (1) energize (2) will NOT C. (1) de-energize (2) will D. (1) de-energize (2) will NOT Friday, March 04, 2016 10:17:05 AM 8

1603 NRC RO Exam

9. Given the following plant conditions:

- Unit 1 tripped from 100% power due to an inadvertent Feedwater Isolation

- 6.9 kV Shutdown Board 1A-A is deenergized and cannot be reenergized

- The 1B-B charging pump is out of service for motor bearing replacement

- All S/G NR levels are 5% and lowering

- RCS pressure is 2235 psig and stable

- The crew has not been able to establish AFW flow per E-0, "Reactor Trip or Safety Injection"

- The SRO has just announced that the Heat Sink status tree is Red Which ONE of the following identifies the action(s) the crew will take first to establish RCS cooling after entering FR-H.1, "Loss of Secondary Heat Sink?"

A. Establish flow to at least one S/G using a MFW pump B. Depressurize at least one S/G and align HPFP to the depressurized S/G(s)

C. Establish RCS feed and bleed using the 1B-B SI pump and both PZR PORVs D. Depressurize at least one S/G and establish condensate flow to the depressurized S/G(s)

Friday, March 04, 2016 10:17:05 AM 9

1603 NRC RO Exam

10. Given the following plant conditions:

- Unit 1 was operating at 100% power when a loss of all 161kv and 500kv lines occurred.

- Both 1A-A and 1B-B D/Gs failed to automatically and manually start.

- The operating crew is responding in accordance with ECA-0.0, "Loss of All AC Power"

- Subsequently off-site power has been restored to the Start Bus 1A and 1B

- Neither shutdown board is re-energized.

- The following indications are observed:

- All 480 V transformer breaker indicating lights for XFMR 1A-A, XFMR 1A1-A and XFMR 1A2-A all indicate RED

- All 480 V Transformer breaker indicating lights for XFMR 1B-B, XFMR 1B1-B and XFMR 1B2-B all indicate GREEN In accordance with ECA-0.0, which ONE of the following identifies the 6.9KV shutdown board(s) that will be energized?

A. 6.9KV Shutdown BD 1A-A, ONLY B. 6.9KV Shutdown BD 1B-B, ONLY C. Both D. Neither, until TSC evaluation Friday, March 04, 2016 10:17:05 AM 10

1603 NRC RO Exam

11. Given the following plant conditons:

- Unit 1 is operating at 100% power.

- A Loss of Vital Instrument Power Board 1-I has occurred.

- The Unit has been tripped and control of AFW to loops 1 and 2 is required.

In accordance with AOP-P.03 "Loss of Unit 1 Vital Instrument Power Board", which ONE of the following identifies the required actions to control AFW to loops 1 and 2.

__(1)__ the 1A-A MD AFW pump.

Accident Reset __(2)__ to be depressed to open loops 1 and 2 MDAFW bypass valves.

A. (1) Manually start (2) is required B. (1) Manually start (2) is NOT required C. (1) Verify AMSAC started (2) is required D. (1) Verify AMSAC started (2) is NOT required Friday, March 04, 2016 10:17:05 AM 11

1603 NRC RO Exam

12. Which ONE of the following identifies the transfer scheme associated with120VAC Vital Inverters Static Switch?

If Inverter Transfer back fails to Inverter A. AUTOMATICALLY Must be MANUALLY transferred transfers to the isolimiter back after inverter output voltage returns to normal B. AUTOMATICALLY AUTOMATICALLY transfers back transfers to the isolimiter after a time delay if inverter output voltage returns to normal C. Must be MANUALLY Must be MANUALLY transferred transferred to the isolimiter back after inverter output voltage returns to normal D. Must be MANUALLY AUTOMATICALLY transfers back transferred to the isolimiter after a time delay if inverter output voltage returns to normal Friday, March 04, 2016 10:17:05 AM 12

1603 NRC RO Exam

13. Given the following plant conditions:

- Both Units are at 100% power.

- ERCW is in normal alignment.

- Subseqently: ERCW header 1A & 2A start indicating LOW flow.

- The following MCR alarms are LIT:

MECH EQUIP SUMP LVL HI (1-M-15A, B-6)

UNIT 1 HEADER A PRESSURE LOW (0-M-27A, A-1)

UNIT 2 HEADER A PRESSURE LOW (0-M-27A, B-3)

- NO OTHER alarms are lit associated with the ERCW system.

Which ONE of the following ERCW conditions accounts for the above indications?

REFERENCE PROVIDED A. Supply header 1A/2A has ruptured in the Yard Area.

B. A discharge header has ruptured in the Yard Area.

C. A rupture has occurred upstream of the 2A strainer.

D. A rupture has occurred in the CCW Intake Pumping Station.

Friday, March 04, 2016 10:17:05 AM 13

1603 NRC RO Exam

14. Which ONE of the following completes the statement below?

The reason for the Turbine Driven AFW Pump LCVs SBO backup air supply is to allow the LCVs to be ___(1)___ and the SBO backup air supply will

___(2)___.

A. (1) OPENED (2) require manual alignment locally when needed B. (1) OPENED (2) automatically be supplied when air pressure drops below regulator setpoint C. (1) CLOSED (2) require manual alignment locally when needed D. (1) CLOSED (2) automatically be supplied when air pressure drops below regulator setpoint Friday, March 04, 2016 10:17:05 AM 14

1603 NRC RO Exam

15. Given the following plant conditions:

- Unit 1 is operating at 100% power

- Subsequently, a Loss Of Coolant Accident (LOCA) outside containment has resulted in RCS Subcooling dropping to 0°F.

- The crew has transitioned to ECA-1.2, "LOCA Outside Containment."

In accordance with ECA-1.2, which ONE of the following:

(1) is the initial mitigating strategy and (2) what would be the indication used to confirm the LOCA has been isolated?

A. (1) Verify RHR suction from RCS Isolated (2) Pressurizer level rising B. (1) Verify RHR suction from RCS Isolated (2) RCS pressure rising C. (1) Isolate RHR Cold Leg Injection (2) Pressurizer level rising D. (1) Isolate RHR Cold Leg Injection (2) RCS pressure rising Friday, March 04, 2016 10:17:05 AM 15

1603 NRC RO Exam

16. Given the following plant conditions:

- A LOCA has occurred on Unit 1.

- The crew is implementing ECA-1.1, "Loss of RHR Sump Recirculation."

Which ONE of the following completes the statement below in accordance with EPM-3-ECA-1.1, "Basis Document for ECA-1.1 Loss of RHR Sump Recirculation?"

Initiation of RCS cooldown to Cold Shutdown will be performed ___(1)___ RCS depressurization AND the reason for the RCS depressurization is ___(2)___.

___(1)___ ___(2)___

A. before to reduce the break flow B. before to refill the pressurizer C. after to reduce the break flow D. after to refill the pressurizer Friday, March 04, 2016 10:17:05 AM 16

1603 NRC RO Exam

17. Given the following plant conditions:

- Unit 2 is at 100% power.

- The TDAFW Pump is tagged out of service.

- A Loss of Feedwater causes a reactor trip.

- Coincident with the trip, 6.9KV Shutdown Board 2A-A de-energizes on fault.

Which ONE of the following identifies the SGs that will receive AFW flow and the expected flow rate to those SGs?

A. SGs 1 & 2 being fed at 220 GPM each B. SGs 1 & 2 being fed at 440 GPM each C. SGs 3 & 4 being fed at 220 GPM each D. SGs 3 & 4 being fed at 440 GPM each Friday, March 04, 2016 10:17:05 AM 17

1603 NRC RO Exam

18. Given the following plant conditions:

- Unit 1 is operating at 80% power.

- Due to grid disturbances the crew had entered AOP-P.07, "Degraded Grid Conditions or Generator Voltage Regulator Malfunction."

- Grid frequency has held steady at 59 Hz for twenty minutes.

- The Unit Supervisor directs the OATC to trip the reactor.

In accordance with AOP-P.07, "Degraded Grid Conditions or Generator Voltage Regulator Malfunction," which ONE of the following identifies the reason for this required action?

A. The Tech Spec limit for frequency on a shutdown board has been exceeded.

B. To prevent exceeding improper bearing loading and turbine misalignment.

C. The auto reactor trip setpoint for RCP underfrequency has been exceeded.

D. To prevent exceeding 25% of lifetime limit of off-frequency operation of LP turbine.

Friday, March 04, 2016 10:17:05 AM 18

1603 NRC RO Exam

19. Given the following plant conditions:

- A Reactor Trip occurred on Unit 1.

- Due to excessive RCS cooldown, the crew is implementing EA-68-4, Section 4.2, "Emergency Boration from BAT".

- After placing 1-HS-62-138A, Emergency Boration FCV in OPEN, the OATC released the handswitch after observing flow indicated on 1-FI-62-137A, Emerg Boration Flow.

- Two minutes later, the OATC observed both 1-HS-62-138A RED and GREEN lights LIT and flow stable at 50 gpm.

Which ONE of the following identifies the status of FCV-62-138, Emergency Boration FCV and the corresponding emergency boration flow rate?

FCV-62-138...

A. stopped opening when the handswitch was released and the flow rate is BELOW the minimum required.

B. stopped opening when the handswitch was released and the flow rate is ABOVE the minimum required.

C. should be full open but has stopped due to thermal overload and the flow rate is BELOW the minimum required.

D. should be full open but has stopped due to thermal overload and the flow rate is ABOVE the minimum required.

Friday, March 04, 2016 10:17:05 AM 19

1603 NRC RO Exam

20. Given the following plant conditions:

- Unit 1 is at 100% power.

- Pressurizer Level Channel Selector, 1-XS-68 339E, is in the LT-68-339 & 335 position.

- Subsequently, the REFERENCE LEG for 1-LI-68-335 develops a leak.

Which ONE of the following identifies the short term (25 to 30 min.) response to this condition?

1-LI-68-339 level indication will __(1)__ and 1-LI-68-335 level indication will__(2)__.

A. (1) Rise (2) Rise B. (1) Rise (2) Lower C. (1) Remain the same (2) Rise D. (1) Remain the same (2) Lower Friday, March 04, 2016 10:17:05 AM 20

1603 NRC RO Exam

21. Given the following plant conditions:

- Unit 2 is in Mode 6.

- The core is being off-loaded.

- It has just been identified (and verified) that the RCS boron concentration is 1975 ppm.

- The refueling boron concentration required by the COLR is 2000 ppm.

Which ONE of the following completes the statement below?

The crew is required to ...

A. initiate boration and suspend positive reactivity changes.

B. suspend core alterations and establish containment integrity.

C. initiate boration and enter AOP-M.04 "Refueling Malfunctions".

D. suspend positive reactivity changes and establish containment intergrity.

Friday, March 04, 2016 10:17:05 AM 21

1603 NRC RO Exam

22. Given the following plant conditions:

- Unit 1 was at 100% power.

- Subsequently, a Steam Generator Tube Leak develops and the crew enters AOP-R.01, Steam Generator Tube Leak.

- A unit shutdown is commenced in accordance with AOP-C.03, "Rapid Shutdown Or Load Reduction," with reactor power currently at 85%.

- Current plant conditions are:

- PZR Level is 55% and stablized

- Charging flow is 105 gpm

- RCP seal leak off is 3 gpm per pump

- RCP seal injection is 8 gpm per pump

- Letdown is isolated Which ONE of the following completes the statement below?

The estimated magnitude of the tube leak is ___(1)___ gpm and leak rate will

___(2)___ as power is reduced.

A. (1) 93 (2) lower B. (1) 93 (2) remain the same C. (1) 125 (2) remain the same D. (1) 125 (2) lower Friday, March 04, 2016 10:17:05 AM 22

1603 NRC RO Exam

23. Given the following plant conditions:

- Unit 1 reactor is at 100% power.

- Containment entry is in progress for maintenance.

- The following annunciators on 1-M12-C are received:

- LWR PERS ACCESS OUTER DR LOCK

- LWR PERS ACCESS INNER DR LOCK

- UPR/LWR AIR LOCK BREACH

- Containment pressure has equalized with the Aux. Building.

- Containment pressure currently indicates 0.18 psid.

- It is determined that the overall containment leakage rate has been exceeded.

Based on the conditions above, which ONE of the following identifies the Tech Spec(s) with actions required to be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ?

A. TS 3.6.2 CONTAINMENT AIR LOCKS, only B. TS 3.6.1 CONTAINMENT and TS 3.6.4 CONTAINMENT PRESSURE C. TS 3.6.1 CONTAINMENT and TS 3.6.2 CONTAINMENT AIRLOCKS D. TS 3.6.2 CONTAINMENT AIR LOCKS and TS 3.6.4 CONTAINMENT PRESSURE Friday, March 04, 2016 10:17:05 AM 23

1603 NRC RO Exam

24. Given the following plant conditions:

- Due to a fire, the Main Control Room has been evacuated.

- The crew has implemented AOP-C.04, "Shutdown From Auxiliary Control Room," and have commenced a cooldown of Unit 1.

Which ONE of the following identifies the required procedure actions to control PZR level within the operating band?

Charging flow will be via __(1)__ path and letdown will be via __(2)__ path.

A. (1) its normal (2) its normal B. (1) its normal (2) excess letdown C. (1) seal injection (2) its normal D. (1) seal injection (2) excess letdown Friday, March 04, 2016 10:17:05 AM 24

1603 NRC RO Exam

25. Given the following plant conditions:

- Unit 2 is operating at 100%

Which one of the following identifies...

(1) the minimum DOSE EQUIVALENT Xe-133 activity value that will require entry into AOP-R.06, "High RCS Activity,"

and (2) the reason for contacting Chemistry during performance of AOP-R.06?

A. (1) > 1200.0 microCi/gm (2) To ensure the Fuel Reliability Assessment Program is implemented.

B. (1) > 1200.0 microCi/gm (2) To recommend letdown alignment for maximizing the cleanup of the RCS.

C. (1) > 1612.6 microCi/gm (2) To recommend letdown alignment for maximizing the cleanup of the RCS.

D. (1) > 1612.6 microCi/gm (2) To ensure the Fuel Reliability Assessment Program is implemented.

Friday, March 04, 2016 10:17:05 AM 25

1603 NRC RO Exam

26. Given the following plant conditions:

- Unit 1 was operating at 100% power.

- Subsequently, the unit has experienced a reactor trip and loss of offsite power.

- The crew is performing ES-0.4, "Natural Circulation Cooldown With Steam Void in Vessel (Without RVLIS)".

While performing RCS depressurization steps in ES-0.4, which ONE of the following explains a function served by using the Pressurizer heaters to repressurize the RCS by 100 psig when Pressurizer level exceeds 90%?

A. Assists in cooling the upper head region of the vessel by collapsing the steam void.

B. Maintains Pressurizer conditions that allow restarting the Reactor Coolant Pumps when power is restored.

C. Provides exchange of liquid in the pressurizer to maintain Pressurizer and RCS boron concentrations within 50 ppm.

D. Ensures PZR liquid is at saturated conditions to limit the rate of pressure reduction when lowering PZR level.

Friday, March 04, 2016 10:17:05 AM 26

1603 NRC RO Exam

27. Given the following plant conditions:

- Unit 1 is operating at 100% power

- Subsequently, a small break LOCA occurs requring a Reactor trip and SI

- Current plant conditions require the crew to implement FR-P.1, "Pressurized Thermal Shock" While performing the steps of FR-P.1, after verifying adequate subcooling and RVLIS level, the crew is directed to establish normal charging to _______________.

A. allow use of auxiliary spray in the event the RCPs cannot be used during RCS depressurization.

B. reduce subsequent RVLIS minimum level requirements and thereby allow RCP restart to equalize system temperature.

C. eliminate ECCS flow as a source of RCS cooldown and to eliminate the possibility of SI causing a subsequent repressurization.

D. reduce unnecessary injection flow because subsequent minimum values for subcooling will be lower than normal SI termination criteria.

Friday, March 04, 2016 10:17:05 AM 27

1603 NRC RO Exam

28. Given the following plant conditions:

- Unit 1 is in Mode 3.

- RTBs are closed

- RCPs #2 & #3 are in operation

- USST 1A and USST 1B are out of service for corrective maintenance

- Maintenance presonnel are performing relay calibrations on the 1B Start Bus

- Subsequently, the 1B Start Bus trips out on differential relay actuation Which ONE of the following completes the statement below?

In accordance with Tech Spec 3.4.5, RCS Loops - Mode 3, _______ .

A. LCO met NO action(s) required B. the RTBs must be opened within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. at least 1 RCP must be restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D. immediately suspend any operation that would add positive reactivity Friday, March 04, 2016 10:17:05 AM 28

1603 NRC RO Exam

29. Given the following plant conditions:

- Unit 1 is in Mode 5 with the PZR solid.

- Train "A" RHR is aligned to provide shutdown cooling.

- An equipment malfunction occurs causing RCS pressure to rise.

- 1A-A RHR pump has just been tripped.

- It is reported that RCS pressure is 375 psig and rising.

In accordance with AOP-R.03, "RHR System Malfunctions," which ONE of the following identifies the RCS pressure at which FCV-74-1 & FCV-74-2, RHR Suction from Loop 4 hot leg, are closed and the reason for this action?

A. 380 psig, to prevent LTOP from initiating.

B. 410 psig, to ensure RCP seals are not damaged.

C. 450 psig, to prevent inventory loss through the suction relief valve.

D. 600 psig, to prevent over-pressurization of the PRT.

Friday, March 04, 2016 10:17:05 AM 29

1603 NRC RO Exam

30. Given the following plant conditions:

- Unit 2 was manually tripped and Safety Injection initiated from 100% power due to a Steam Generator Tube Rupture.

- Coincident with the reactor trip, all four (4) Unit 2 6.9KV Unit boards lock out.

- When attempting to de-pressurize the RCS, neither PZR PORV would open.

- The crew decides to use Auxiliary Spray to depressurize the RCS.

Which ONE of the following identifies the operational concern of using Auxiliary spray?

A. an additional loss of reactor coolant will occur.

B. excessive thermal stresses of spray nozzle may occur.

C. excessive thermal stresses of the PZR surge line will occur.

D. the rate of RCS pressure reduction will be difficult to control.

Friday, March 04, 2016 10:17:05 AM 30

1603 NRC RO Exam

31. Given the following plant conditions:

- Unit 1 is in solid plant operation

- 1A-A RHR pump is in service for shutdown cooling

- Charging and RHR letdown are in service

- The air line to Letdown Pressure Control Valve PCV-62-81 fails Which ONE of the following identifies how the plant will respond to this failure?

A. Charging flow will auto increase to maintain constant RCS pressure.

B. RCS pressure will increase until the Cold Overpressure Protection system actuates.

C. RCS pressure will decrease due to letdown line flow being greater than charging flow.

D. Train A RHR flow will increase resulting in RHR pump discharge relief valve lifting.

Friday, March 04, 2016 10:17:05 AM 31

1603 NRC RO Exam

32. Given the following plant conditions:

- Unit 1 is at 100% power.

- Subsequently, a LOCA has occurred.

- RCS pressure dropped rapidly to 1300 psig.

- While performing ES.05, "Equipment Verfications, step 11. Monitor ECCS operation," the following indications associated with 1B-B SI pump is observed:

- the "RED" indicating light on the pump control switch is LIT

- motor amps are at minimum

- flow is off-scale low

- discharge pressure is equal to that of 1A-A SI pump Based on the above indications, which ONE of the following completes the statement below?

The 1B-B SI pump indications __(1)__ expected and in accordance with ES-0.5, the operators are directed to __(2)__ .

A. (1) are (2) continue with ES-0.5 actions, no further action associated with SI pumps is required B. (1) are (2) ensure SI pump recirc valves FCV-1-63-3, FCV-1-63-4, and 1-63-175 are closed C. (1) are NOT (2) ensure SI pump valve alignment is correct before proceeding on in ES-0.5 D. (1) are NOT (2) close FCV-63-153, SI Pump B-B discharge crosstie before continuing on in ES-0.5.

Friday, March 04, 2016 10:17:05 AM 32

1603 NRC RO Exam

33. Given the following plant conditions:

- Unit 2 was manually tripped from 100% due to a small break LOCA

- A loss of Off-Site power occurred concurrently with the reactor trip

- Exosensor displays are not available

- The crew is performing ES-1.2, "Post LOCA Cooldown and Depressurization,"

Step 17, Depressurize RCS to establish PZR level greater than 20%

- Core Exit Temperature (auctioneered high core quadrant average) is 582°F

- All RCS Hot Leg Temperatures (Thot) are 562°F

- RCS average temperature (Tave) is 557°F

- RCS wide range pressure is 2200 psig

- Containment pressure is 1.0 psig Which ONE of the following identifies the approximate (+/- 5 psig) RCS pressure at which RCS subcooling may be lost (subcooling margin equals 0°F)?

A. 1347 psig B. 1332 psig C. 1167 psig D. 1120 psig Friday, March 04, 2016 10:17:05 AM 33

1603 NRC RO Exam

34. In accordance with 1-SO-68-5, "Pressurizer Relief Tank," which ONE of the following completes the statement below?

The maximum level allowed in the Pressurizer Relief Tank (PRT) before it is required to be drained is __(1)__ and the RCDT Pump B __(2)__ when 1-FCV-68-310, PRT Drain to RCDT, is opened.

A. (1) 64%

(2) auto-starts B. (1) 64%

(2) must be manually started C. (1) 88%

(2) auto-starts D. (1) 88%

(2) must be manually started Friday, March 04, 2016 10:17:05 AM 34

1603 NRC RO Exam

35. Given the following plant conditions:

- Both units are at 100% power.

- Spent Fuel Pool Cooling is aligned to Unit 2

- A spurious SI signal is generated on Unit 2 Which ONE of the following identifies the heat exchanger(s) that will lose Component Cooling System (CCS) cooling water?

A. The Spent Fuel Pool Cooling Heat Exchanger.

B. The Reactor Coolant Pump Seal (Leakoff) Water Heat Exchangers.

C. The CVCS Excess Letdown Heat Exchanger.

D. The Reactor Coolant Pump Thermal Barrier Heat Exchangers.

Friday, March 04, 2016 10:17:05 AM 35

1603 NRC RO Exam

36. Given the following plant conditions:

- Unit 1 is operating at 100% power

- Subsequently, a loss of off-site power occurs With NO operator action outside of the MCR, which pressurizer heaters are available to control RCS pressure?

A. Group A and Group C heaters will be automatically controlled.

B. Group C and Group D heaters can be manually controlled from M-4.

C. Group A and Group B heaters will be automatically controlled.

D. All heater groups can be manually controlled from M-4.

Friday, March 04, 2016 10:17:05 AM 36

1603 NRC RO Exam

37. Given the following plant conditions:

- Unit 1 is operating at 100% power.

- Channel 3 of the containment "HIGH-HIGH PRESS" pressure switches is out of service for surveillance testing with its bistable BYPASSED.

- The associated channel 3 "HIGH PRESS" bistable has been tripped as allowed by Tech. Specs.

- Subsequently, channel 2 of the containment "HIGH PRESS" pressure switch fails high such that a high pressure signal is initiated.

- Rx Trip and SI actuate.

Which ONE of the following describes the response of the Containment Spray System and the plant to the pressure switch failure?

A. Containment Spray will actuate; Cont. Isolation Phase A actuates.

B. Containment Spray will NOT actuate; Cont. Isolation Phase A actuates.

C. Containment Spray will actuate; Cont. Isolation Phase B actuates.

D. Containment Spray will NOT actuate; Cont. Isolation Phase B actuates.

Friday, March 04, 2016 10:17:05 AM 37

1603 NRC RO Exam

38. Given the following plant conditions:

- Unit 1 is initially at 100% power when an event occurred.

- The crew has just restored power to FCV-63-1, RHR pump suction from RWST, at step 6 of ES-1.3, "Transfer to RHR Containment Sump."

- RWST level is 20% and lowering.

- CNTMT pressure is 1.5 psig and lowering.

- Alarm: LS-63-176 CNTMT LEVEL HI RHR RECIRC (1-M6C-E4) is LIT

- 1-HS-63-72A, CNTMT Sump Suct To RHR Pump 1A, Red light LIT

- 1-HS-63-73A, CNTMT Sump Suct To RHR Pump 1B, Red light LIT

- 1-HS-72-39A, CNTMT Spray Hdr 1A Isol, Green light LIT

- 1-HS-72-2A, CNTMT Spray Hdr 1B Isol, Green light LIT Which ONE of the following completes the statement below?

Based on the above indications the RHR CNTMT Sump suction valves ____(1)____

in the expected positions and the CNTMT Spray Header isolations ___(2)___

in the expected positions.

A. (1) are (2) are B. (1) are (2) are NOT C. (1) are NOT (2) are D. (1) are NOT (2) are NOT Friday, March 04, 2016 10:17:05 AM 38

1603 NRC RO Exam

39. Given the following plant conditions:

- Unit 1 is at 100% power

- Subsequently, a Loss of Off-Site Power occurs

- A steam line break has generated a safety injection signal but Engineered Safety Feature Actuation System (ESFAS) Train "A" did NOT actuate

- Containment pressure indicates 2.9 psig and rising Assuming NO manual actions have been initiated, which ONE of the following identifies a consequence of that failure?

A. 1A-A MDAFW pump will remain in standby.

B. Only the B Train load sequencer will be operating.

C. Only two Main Steam Isolation Valves (MSIV's) will automatically close.

D. Only one Phase A Containment Isolation Valve in each penetration will automatically close.

Friday, March 04, 2016 10:17:05 AM 39

1603 NRC RO Exam

40. Given the following plant conditions:

- Unit 1 is operating at 100% power.

Which ONE of the following statements identifies both the maximum containment ice bed temperature allowed in accordance with 1-SI-OPS-000-002.0, "Shift Logs," and a potential effect of operating above the maximum temperature?

Maximum Temperature. Potential Effect A. 20°F Exceeding 12 psig inside Containment during a LOCA B. 20°F Exceeding 12 psig inside Containment during a Steam Line Break C. 27°F Exceeding 12 psig inside Containment during a LOCA D. 27°F Exceeding 12 psig inside Containment during a Steam Line Break Friday, March 04, 2016 10:17:05 AM 40

1603 NRC RO Exam

41. Given the following plant conditions:

- Unit 2 is operating at 100% power.

- Due to a loss of Lower Compartment Cooling, lower containment temperature has risen from 110°F to 119°F.

- Actions are in progress to restore cooling.

If the temperature continues to rise in containment, which ONE of the following describes the effect on pressurizer level indication?

The controlling pressurizer level channel will indicate slightly...

A. higher than actual level, and remain lower than the cold-calibrated pressurizer level instrument.

B. lower than actual level, and remain lower than the cold-calibrated pressurizer level instrument.

C. higher than actual level, and remain higher than the cold-calibrated pressurizer level instrument.

D. lower than actual level, and remain higher than the cold-calibrated pressurizer level instrument.

Friday, March 04, 2016 10:17:05 AM 41

1603 NRC RO Exam

42. Given the following plant conditions:

- Unit 1 at 100% power.

- An inadvertent Reactor Trip and Safety Injection occurred.

- Ice Condenser System glycol trapped between the inside and outside Containment penetration's return isolation valves expanded due to heating.

Which ONE of the following identifies the system response to the glycol expansion?

A. The penetration's inside glycol isolation valve disks are designed to relieve trapped glycol into the Containment side glycol supply header.

B. The penetration's outside glycol isolation valve disks are designed to relieve trapped glycol into the Auxiliary Building side glycol supply header.

C. A bypass line with a check valve is installed around the penetration's inside isolation valve to relieve trapped glycol into the Containment side glycol supply header.

D. A relief valve is installed between the penetration's inside and outside isolation valves to relieve trapped glycol into the Containment.

Friday, March 04, 2016 10:17:05 AM 42

1603 NRC RO Exam

43. Given the following plant conditions:

- Unit 1 tripped from 100% power due to a LOCA.

- The crew is implementing ES-1.3, "Transfer to RHR Containment Sump,"

and preparing to align the suction of the Containment Spray pumps to the containment sump.

Which ONE of the following identifies an INTERLOCK associated with containment sump level which must be satisfied before 1-FCV-72-23, Containment Spray Pump 1A Suction from Containment Sump will open?

Containment sump level must be at least _____ .

A. 8%

B. 11%

C. 18%

D. 56%

Friday, March 04, 2016 10:17:05 AM 43

1603 NRC RO Exam

44. Given the following plant conditions:

- Unit 1 is in Mode 4 with RCS temperature at 310°F during a plant heatup.

- The MSIV bypass valves are open to warm the Main Steam Lines.

- Differential pressure across the MSIVs is 30 psid.

- The operating crew is planning to open the MSIVs when the steamline deltaP criteria is met.

Which ONE of the following completes the statements below?

In accordance with 1-SO-1-1, "Main Steam System," the maximum pressure differential allowed across an MSIV to allow it to be opened is ___(1)___ and SRO permission ___(2)___ required to open the MSIV at this pressure.

___(1)___ ___(2)___

A. 15 psid is NOT B. 15 psid is C. 25 psid is NOT D. 25 psid is Friday, March 04, 2016 10:17:05 AM 44

1603 NRC RO Exam

45. Given the following plant conditions:

- Unit 2 is in Mode 3

- RCS pressure is 2235 psig

- Tavg is being maintained by the steam dumps in Steam Pressure mode at 1005 psig.

- Atmospheric relief valve controllers have been set per 2-SO-1-1, "Main Steam System."

- All four RCP's are running.

- Subsequently, a complete loss of Condenser vacuum occurs.

Which ONE of the following identifies the value at which RCS Tavg is expected to stabilize? (Assume NO operator action) o A. 547 F B. 549oF C. 552oF D. 554oF Friday, March 04, 2016 10:17:05 AM 45

1603 NRC RO Exam

46. Given the following plant conditions:

- Unit 1 is in Mode 2 performing a plant startup.

- Breaker 523 "MFPT A 250V DC Trip" bus supply breaker is OPEN.

- Breaker 524 "MFPT B 250V DC Trip" bus supply breaker is CLOSED.

- The "B" MFWP turbine is RESET and NOT pumping forward.

- Subsequently, injection water supply pressure drops to <220 psig for 25 seconds before returning to normal.

Which ONE of the following completes the statements below?

The "B" MFWP __(1)__ auto trip.

and the AFW pumps __(2)__ receive an auto start signal.

A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT Friday, March 04, 2016 10:17:05 AM 46

1603 NRC RO Exam

47. Given the following conditions:

- Unit 2 is operating at 100% power.

- Subsequently, instrument failures cause a spurious Main Feedwater Isolation Signal.

- NO Auxiliary Feedwater Pumps start.

- The reactor does NOT trip.

- AMSAC fails to actuate.

Assuming NO operator action, which ONE of the following is the primary concern and why?

A. Loss of RCS integrity caused by an overpressure transient.

B. Main steamline break caused by thermal shock on Steam Generator shell.

C. SG tube rupture caused by high primary-to-secondary differential pressure.

D. Overpower condition caused by the failure of the turbine to receive a trip signal.

Friday, March 04, 2016 10:17:05 AM 47

1603 NRC RO Exam

48. Given the following plant conditions:

- Unit 1 is operating at 100% power

- During the performance of a surveillance test on the TDAFW pump, the following alarm is received:

AUX FWP TURBINE 1A-S MECHANICAL OVERSPEED TRIP (1-M-3C, A-4)

- The cause of the alarm is determined to be 1-FIC-46-57 failed to control the pump outlet flow.

Which ONE of the following identifies:

(1) the setpoint for this alarm AND (2) after the Mechnical Overspeed mechanism is RESET and LATCHED, the action required prior to attempting to restart the TDAFW pump in accordance with 1-SO-3-2, "Auxiliary Feedwater System?

A. (1) 4300 rpm (2) Hold 1-HS-1-51A-S, Trip/Throttle Valve, closed for 10 seconds to clear the overspeed alarm, then open Trip/Throttle valve using 1-HS-51-A-S.

B. (1) 4300 rpm (2) Place speed controller in MANUAL and set controller output at 20%, then open Trip/Throttle valve using 1-HS-1-51A-S.

C. (1) 4900 rpm (2) Hold 1-HS-1-51A-S, Trip/Throttle Valve, closed for 10 seconds to clear the overspeed alarm, then open Trip/Throttle valve using 1-HS-51-A-S.

D. (1) 4900 rpm (2) Place speed controller in MANUAL and set controller output at 20%, then open Trip/Throttle valve using 1-HS-1-51A-S.

Friday, March 04, 2016 10:17:05 AM 48

1603 NRC RO Exam

49. Given the following plant conditions:

- Both units are at 100% power.

- The following annunciator was received on Unit 1:

"120V AC VITAL INVERTER 1-I OR INVERTER 0-I ABNORMAL" (1M-C, A6)

- AUOs were dispatched to the inverters and found the yellow "BYPASS SOURCE SUPPLYING LOAD" light lit on the inverter 1-I.

Which ONE of the following completes the statements below?

The inverter has transferred to the __(1)__ .

and LCO 3.8.7 "Inverters - Operating" __(2)__ be entered.

A. (1) 125V DC Vital Battery Board (2) would B. (1) 125V DC Vital Battery Board (2) would NOT C. (1) Isolimiter (Reg) transformer (2) would D. (1) Isolimiter (Reg) transformer (2) would NOT Friday, March 04, 2016 10:17:05 AM 49

1603 NRC RO Exam

50. Which ONE of the following would indicate that the 125V DC Vital Battery Charger 1 output breaker tripped open?

Panel 1M-C annunciator __(1)__ would alarm and indicator EI-57-92, Batt BD I AMPS, would be indicating __(2)__ from zero.

A. (1) "125V DC VITAL BAT BD I ABNORMAL" (A-5)

(2) upscale B. (1) "125V DC VITAL BAT BD I ABNORMAL" (A-5)

(2) downscale C. (1) "125 V DC VITAL CHGR I FAILURE OR VITAL BAT I DISCHARGE" (A-4)

(2) upscale D. (1) "125 V DC VITAL CHGR I FAILURE OR VITAL BAT I DISCHARGE" (A-4)

(2) downscale Friday, March 04, 2016 10:17:05 AM 50

1603 NRC RO Exam

51. Given the following plant conditions:

- The Diesel Generator 1A-A Day Tank Fuel Oil Transfer Pump #1 is running in automatic due to a low level in a 1A-A Day Tank caused when maintenance pumped out the day tank .

- The D/G 1A-A is NOT running at this time.

- Subsequently, 6.9Kv Unit Bd 1B trips on a ground fault.

Which ONE of the following completes the statement below?

The Diesel Generator Day Tank Fuel Oil Transfer Pump will .....

A. continue to run since it is DC powered from the D/G battery.

B. continue to run since it is powered from "B" train shutdown power.

C. stop and require manual restart after 6.9 kv Shutdown Bd 1A-A is energized.

D. stop and after the 1A-A D/G ties onto the 1A-A 6.9 kv Shutdown Bd., the pump will restart.

Friday, March 04, 2016 10:17:05 AM 51

1603 NRC RO Exam

52. Given the following plant conditions:

- Unit 1 is operating at 100% power

- Total primary to secondary leakage is 70 gpd

- Identified RCS leakage is 0.18 gpm

- Unidentified RCS leakage is 0.2 gpm

- Pzr level, VCT level, charging flow, and letdown flow are all stable Which ONE of the following conditions would provide the first indications in the control room of a developing fuel element defect?

A. Annunciator "1-RA-272A UPPR IN CNTMT HI RAD" alarms and a rapidly increasing count rate on 1-RM-90-112A/B/C "Upper Containment Air Monitor."

B. A slowly increasing count rate on 1-RM-90-119 "Condenser Vacuum Exhaust Monitor" and NO increase in count rate on 1-RM-90-106A/B "Lower Containment Air Monitor."

C. A slowly increasing count rate on 1-RM-90-130A and -131A "Containment Purge Exhaust Monitors" and Annunciator "1-RA-272A UPPR IN CNTMT HI RAD" alarms.

D. A slowly increasing count rate on 1-RM-90-106A/B "Lower Containment Air Monitor" and a slowly increasing count rate on 1-RM-90-119 "Condenser Vacuum Exhaust Monitor."

Friday, March 04, 2016 10:17:05 AM 52

1603 NRC RO Exam

53. Given the following plant conditions:

- Both Units operating at 100% power

- All systems aligned normally If a large ERCW leak developed at the inlet to the 1A1 CCS Heat Exchanger, which ONE of the ERCW Headers would have increased flow, and when the leak was isolated, how would the 1A and 2A ERCW header pressures be effected?

Header with Effect on Header Pressure Flow Increase after leak is isolated A. 1A Both 1A and 2A header pressures would increase B. 1A Only the 1A header pressure would increase C. 2A Both 1A and 2A header pressures would increase D. 2A Only the 2A header pressure would increase Friday, March 04, 2016 10:17:05 AM 53

1603 NRC RO Exam

54. Given the following plant conditions:

- Unit 1 is in Mode 5 with 6.9kV Shutdown Board 1A-A tagged for maintenance.

- Subsequently, 6.9kV Shutdown Board 2B-B trips and locks out due to relay operation.

Which ONE of the following identifies the status of the Auxiliary Air Compressor power supplies?

A. Both Auxiliary Air Compressors have a power supply available.

B. Neither Auxiliary Air Compressor has a power supply available.

C. Only the Auxiliary Air Compressor A-A has a power supply available.

D. Only the Auxiliary Air Compressor B-B has a power supply available.

Friday, March 04, 2016 10:17:06 AM 54

1603 NRC RO Exam

55. Given the following plant conditions:

- Unit 2 experienced a manual Safety Injection (SI).

- Containment Purge Rad Monitor, 2-RM-90-130, was in high rad alarm but has been reset.

- Containment Purge Rad Monitor, 2-RM-90-131, indicates normal.

- Containment Vent Isolation occurred on Train A.

- Containment Vent Isolation did NOT occur on Train B.

- Phase A has been RESET.

- SI signal has NOT been RESET.

Which ONE of the following identifies the status of the Containment Vent Isolation (CVI) system?

The CVI ____________________ and __________________________.

A. should have occurred on A and B Train; the CVI can be reset with the SI signal present.

B. should have occurred on A and B Train; the SI signal must be reset before the CVI can be reset.

C. should NOT have occurred on B Train; the CVI can be reset with the SI signal present.

D. should NOT have occurred on B Train; the SI signal must be reset before the CVI can be reset.

Friday, March 04, 2016 10:17:06 AM 55

1603 NRC RO Exam

56. Given the following plant conditions:

- Unit 2 is at 100% power.

- Subsequently, a Reactor trip and SI have actuated.

- RCS pressure is 300 psig and LOWERING.

- PZR level is offscale LOW.

- RCS temperature is 504°F and LOWERING.

- Containment pressure is 6 psig and RISING slowly.

- S/G pressures are 690 psig and LOWERING slowly.

- Crew is performing E-0, "Reactor Trip or Safety Injection".

Which ONE of the following identifies the cause of these conditions?

A. RCS Cold Leg Break.

B. PZR Safety Valve failed OPEN.

C. Main Feed Line Break inside containment.

D. Main Steam Line Break inside containment.

Friday, March 04, 2016 10:17:06 AM 56

1603 NRC RO Exam

57. Which ONE of the following identifies all nuclear instruments that are powered from 120V AC Vital Instrument Power Board 1-I?

A. N-31 and N-41 only B. N-35 and N-41 only C. N-31 and N-35 only D. N-31, N-35, and N-41 Friday, March 04, 2016 10:17:06 AM 57

1603 NRC RO Exam

58. GIven the following plant conditions:

- Unit 1 is at 100% power

- Subsequently, a small break LOCA has occurred.

- Core exit thermocouples (T/C) are being monitored by the STA.

In accordance with GOI-6, "Apparatus Operations," which ONE of the following identifies both the indication range and the display code which indicates that a Core Exit Thermocouple is out of electrical limits?

Indication Range Code for out of electrical limits A. 200 - 2300 F "XXX "

B. 200 - 2300 F " ? " (question mark)

C. 0 - 3000 F " ? " (question mark)

D. 0 - 3000 F " XXX "

Friday, March 04, 2016 10:17:06 AM 58

1603 NRC RO Exam

59. Given the following plant conditions:

- Unit 1 has experienced a Large break LOCA.

- FR-C.1,"Inadequate Core Cooling," is being implemented.

- Containment pressure is 10 psig and slowly lowering.

- Containment hydrogen concentration is 6.5% and slowly rising.

Which ONE of following identifies the Hydrogen Recombiner operation?

Hydrogen recombiner operation....

A. is not allowed because of the operation of containment spray.

B. is allowed provided the hydrogen igniters have previously been placed in service.

C. is allowed, however the maximum power setting is limited.

D. is not allowed because it may cause a sudden rise in containment pressure.

Friday, March 04, 2016 10:17:06 AM 59

1603 NRC RO Exam

60. Given the following plant conditions:

- Unit 1 core has been off-loaded.

- Irradiated fuel shuffles are in progress in the spent fuel pool.

- Main Control Room Radiation Monitor, 0-RM-90-125, fails due to an instrument malfunction.

Which ONE of the following identifies if the radiation monitor failure would require an LCO entry on Unit 1 and the effect the failure would have on the movement of irradiated fuel in the spent fuel pit?

LCO Condition entry Fuel Movement A. Required Can continue B. Required Must be stopped C. NOT required Can continue D. NOT required Must be stopped Friday, March 04, 2016 10:17:06 AM 60

1603 NRC RO Exam

61. Given the following plant conditions:

- Unit 1 is at 100% power.

- A reactor trip is initiated by operator action.

- RTB "B" does NOT open on the trip.

Which ONE of the following identifies the expected response of the steam dump system?

The steam dumps will attempt to maintain the RCS Tavg at __(1)__ with the

__(2)__ controller.

A. (1) 547°F (2) reactor trip B. (1) 547°F (2) load rejection C. (1) 552°F (2) reactor trip D. (1) 552°F (2) load rejection Friday, March 04, 2016 10:17:06 AM 61

1603 NRC RO Exam

62. Which ONE of the following identifes:

(a) how main steam header pressure will respond as turbine load is raised from 50%

to 70%

and (b) the method of maintaining Tavg on program which would result in the value for MTC being the MOST negative as turbine load was raised?

A. (a) header pressure will lower (b) maintain rod position constant, while lowering Boron concentration to maintain Tavg on program B. (a) header pressure will lower (b) withdraw control rods to maintain Tavg on program, while holding Boron concentration constant C. (a) header pressure will rise (b) maintain rod position constant, while lowering Boron concentration to maintain Tavg on program D. (a) header pressure will rise (b) withdraw control rods to maintain Tavg on program, while holding Boron concentration constant Friday, March 04, 2016 10:17:06 AM 62

1603 NRC RO Exam

63. Given the following plant conditions;

- Unit 1 is operating at 100% power when CBP 1A trips.

- The operating crew enters AOP-S.04, "Condensate or Heater Drains Malfunction."

- Investigation determines the pump to be damaged and will be out of service for several days.

Which ONE of the following completes the statements below in accordance with AOP-S.04?

An immediate load reduction may be required to maintain MFP suction pressures greater than a minimum of __(1)__ psig.

With the pump being out of service for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the procedure directs an evaluation of a power reduction to at least less than __(2)__ to reduce the risk of a unit trip if any additional secondary plant malfunctions occurs.

(1) (2)

A. 250 85%

B. 250 75%

C. 320 85%

D. 320 75%

Friday, March 04, 2016 10:17:06 AM 63

1603 NRC RO Exam

64. Given the following plant conditions:

- Both Units are operating at 100% power.

- 0-RM-90-103A, Spent Fuel Pit Radiation Monitor, fails HIGH.

Which ONE of the following indentifies the expected plant response?

A. ONLY Train B Aux Building Isolation dampers close; ONLY Train B Aux Building General Supply, Exhaust and Fuel Handling exhaust fans trip.

B. ONLY Train B Aux Building Isolation dampers close; ALL Aux Building General Supply, Exhaust and Fuel Handling exhaust fans trip.

C. ONLY Train A Aux Building Isolation dampers close; ONLY Train A Aux Building General Supply, Exhaust and Fuel handling exhaust fans trip.

D. BOTH Train A and Train B Aux Building Isolation dampers close; ALL Aux Building General Supply, Exhaust, and Fuel handling exhaust fans trip.

Friday, March 04, 2016 10:17:06 AM 64

1603 NRC RO Exam

65. Given the following plant conditions:

- Maintenance personnel report that a Service Air connection providing air to a pneumatic grinder has broken and cannot be isolated.

- Air Header Pressure indications are as follows:

PI-32-104A, AUX CONT AIR HDR A PRESS 92 psig PI-32-105A, AUX CONT AIR HDR B PRESS 92 psig PI-32-200, CONT AIR HDR PRESS 94 psig and slowly lowering PI-33-199, SERV AIR HDR PRESS 90 psig and slowly lowering Which ONE of the following completes the statements below?

(1) At the current pressures, PCV-33-4, SERVICE AIR ISOL ___(1)__ open.

(2) If PCV-33-4 automatically closes, once the Service Air Header is repressurized, the valve ___(2)___ .

A. (1) is (2) must be reset before it will open B. (1) is (2) will reopen automatically C. (1) is NOT (2) must be reset before it will open D. (1) is NOT (2) will reopen automatically Friday, March 04, 2016 10:17:06 AM 65

1603 NRC RO Exam

66. Which ONE of the following completes the statement below?

Concerning the operation of the Steam Dump Control System, when the "D" solenoids are energized they ____ .

A. allow the steam dump valves to respond more quickly when needed B. prevent the steam dump valves from opening if the condenser is not available C. align control air to supply for modulation control when the steam dumps are armed D. allow the steam dump cooldown valves to open when Tavg is below the Lo-Lo Tavg interlock Friday, March 04, 2016 10:17:06 AM 66

1603 NRC RO Exam

67. Which ONE of the following identifies the alternate locations available for charging flow control and indication outside of the Main Control Room?

Aux Control Room Locally in the Aux Building (1-L-10) (1-L-112A)

A. Controller functions and the flow No control function on panel, indication reads only with Nor-Aux flow indication only switch in AUX B. Controller functions and the flow Panel has both controller indication reads only with Nor-Aux function and flow indication switch in AUX C. Controller functions only with No control function on panel, Nor-Aux switch in AUX flow indication only Indication reads with Nor-Aux switch in either position D. Controller functions only with Panel has both controller Nor-Aux switch in AUX function and flow indication Indication reads with Nor-Aux switch in either position Friday, March 04, 2016 10:17:06 AM 67

1603 NRC RO Exam

68. Given the following plant conditions:

- Unit 1 is preparing for a startup with the RCS at 540°F.

Which ONE of the following completes the statements below?

The value for Safety Limit 2.1.2, "RCS Pressure SL" is ___(1)___.

AND Violation of SL 2.1.2 requires RCS pressure to be reduced to less than the limit within ___(2)___ from the time the limit was violated.

___(1)___ ___(2)___

A. 2485 psig 5 minutes B. 2485 psig 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. 2735 psig 5 minutes D. 2735 psig 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Friday, March 04, 2016 10:17:06 AM 68

1603 NRC RO Exam

69. Given the following plant conditions:

- A main control room annunciator, 2-M15-A, A-4, PdS-27-13B TRAV SCREEN 2B DIFF PRESS HI, has alarmed repeatedly over the past hour.

- Traveling Screen delta P on 2-PDI-27-13A reads 1.5 in. H20 and steady.

- An AUO is dispatched to CCW pumping station several times and reports:

- local screen delta P reads 1.5 in. H2O

- there are NO visible obstructions

- Screen wash pumps and traveling screens are NOT running Based on the given conditions, which ONE of the following completes the statements below?

In accordance with OPDP-4, "Annunciator Disablement," this alarm __(1)__ the definition of a nuisance alarm.

and Any annuciator that is disabled due to being a nuisance alarm, ___(2)___

required to be logged in the narrative log.

A. (1) meets (2) is B. (1) meets (2) is NOT C. (1) does NOT meet (2) is D. (1) does NOT meet (2) is NOT Friday, March 04, 2016 10:17:06 AM 69

1603 NRC RO Exam

70. Which ONE of the following completes the statement below?

A SQN plant worker has lifetime accumulated dose of 900 mrem as documented on an NRC form 4.

In accordance with NPG-SPP-5.1, "Radiological Controls," the worker's yearly administrative whole body dose limit is __(1)__ and to exceed the administrative dose limit __(2)__ approval is required.

A. (1) .5 Rem TEDE (2) Rad Protection Manager B. (1) .5 Rem TEDE (2) Shift Manager C. (1) 1 Rem TEDE (2) Rad Protection Manager D. (1) 1 Rem TEDE (2) Shift Manager Friday, March 04, 2016 10:17:06 AM 70

1603 NRC RO Exam

71. A Monitor Tank release is in progress.

- 0-RCV-77-43, Liquid Radwaste Release Valve, closed to terminate the release.

Which ONE of the following identifies the conditions that would directly cause a Monitor Tank release to automatically terminate?

I. Less than 2 ERCW pumps per train running II. Loss of power to 0-RCV-77-43, Liquid Radwaste Release Valve III. 0-RM-90-122, Liquid Radwaste Release Monitor low flow (< 2.5 gpm)

A. II ONLY B. II and III ONLY C. I and II ONLY D. I, II, and III Based on a question during the exam: How many pumps are running in each train.

The applicants were informed that 2A and 1B ERCW pumps are running.

Friday, March 04, 2016 10:17:06 AM 71

1603 NRC RO Exam

72. Prior to an entry into lower containment being made, which ONE of the following identifies the verifications that are required relative to the incore flux detector placement and tagging?

Detector Placement Tagged with a...

A. Storage position, only Caution Order B. Storage position, only Hold Order C. Storage position or inserted Caution Order to within 10 feet of the core D. Storage position or inserted Hold Order to within 10 feet of the core Friday, March 04, 2016 10:17:06 AM 72

1603 NRC RO Exam

73. Which ONE of the following sets of plant paramaters will result in a RED path on the Heat Sink Status Tree?

A. Containment Pressure is 2 psig S/G 1 S/G 2 S/G 3 S/G 4 NR Level 40% 15% 28% 28%

WR Level ---- ---- ---- ----

AFW Flow 60gpm 130 gpm 80 gpm 50 gpm B. Containment Pressure is 2 psig S/G 1 S/G 2 S/G 3 S/G 4 NR Level ---- ---- 5% 8%

WR Level 0% 0% ---- ----

AFW Flow 0 gpm 0 gpm 190 gpm 255 gpm C. Containment Pressure is 3 psig S/G 1 S/G 2 S/G 3 S/G 4 NR Level ---- ---- 24% 23%

WR Level 20% 20% ---- ----

AFW Flow 100 gpm 100 gpm 100 gpm 100 gpm D. Containment Pressure is 3 psig S/G 1 S/G 2 S/G 3 S/G 4 NR Level ---- 22% 21% 23%

WR Level 0% ---- ---- ----

AFW Flow 0 gpm 160 gpm 155 gpm 140 gpm Friday, March 04, 2016 10:17:06 AM 73

1603 NRC RO Exam

74. Which ONE of the following identifies...

(1) the Emergency Response Organization responsible for dispatching Emergency Response Teams during a plant emergency and (2) the lowest level emergency that will result in the emergency center being required to be staffed?

(1) (2)

A. Technical Support Center Alert B. Technical Support Center SAE C. Operations Support Center Alert D. Operations Support Center SAE Friday, March 04, 2016 10:17:06 AM 74

1603 NRC RO Exam

75. Given the following plant condtions:

- Unit 1 is shutting down and is currently 230°F

- 1A RHR train is being placed in service per 0-SO-74-1, "Residual Heat Removal System."

- RHR Letdown has been placed in service at maximum flow.

- CCS flow thru the 1A-A RHR heat exchanger is 1000 gpm.

- FCV-63-93, RHR Pump A-A Discharge to Loops 2 and 3 Cold Leg, has just been opened.

- Annunciator "RHR HX A OUTLET TEMPERATURE HIGH," (0-M27-B-A, E-6) alarms.

Which ONE of the following identifies the valve leaking by that will result in the alarm and the operator action to mitigate in accordance with the Annunciator Response?

Condition Action to mitigate A. FCV-74-16, RHR Hx 1A Outlet Remove RHR Letdown from service.

Flow Control Valve B. FCV-74-32, RHR Hx 1A and 1B Remove RHR Letdown from service.

Bypass Flow Control Valve C. FCV-74-16, RHR Hx 1A Outlet Increase CCS flow through the 1A-A RHR Flow Control Valve Heat Exchanger.

D. FCV-74-32, RHR Hx 1A and 1B Increase CCS flow through the 1A-A RHR Bypass Flow Control Valve Heat Exchanger.

You have completed the test!

Friday, March 04, 2016 10:17:06 AM 75

ANSWER KEY REPORT for 1603 NRC RO Exam Test Form: 0 Answers

ID Points Type 0 1 007 EK2.03 501 1.00 MCS B 2 009 EK.2.03 502 1.00 MCS B 3 015 AK3.03 503 1.00 MCS C 4 022 AG2.2.4 104 1.00 MCS B 5 025 AK1.01 505 1.00 MCS C 6 026 AA2.01 506 1.00 MCS C 7 027 AG2.1.7 107 1.00 MCS A 8 029 EK2.06 8 1.00 MCS A 9 054 AA1.04 9 1.00 MCS C 10 055 EA1.07 510 1.00 MCS A 11 057 AA2.20 311 1.00 MCS C 12 058 AA1.02 12 1.00 MCS B 13 062 AG2.4.47 13 1.00 MCS C 14 065 AA2.07 514 1.00 MCS C 15 W/E04 EK1.2 215 1.00 MCS B 16 W/E11 EK3.2 16 1.00 MCS A 17 W/E05 EK1.1 517 1.00 MCS C 18 077 AK3.01 18 1.00 MCS D 19 024 AG2.1.31 19 1.00 MCS B 20 028 AK1.01 520 1.00 MCS C 21 036 AK1.02 121 1.00 MCS A 22 037 AA2.12 22 1.00 MCS A 23 069 AK2.03 223 1.00 MCS C 24 068 AA1.12 124 1.00 MCS D 25 076 AK3.06 325 1.00 MCS B 26 W/E10 EG2.4.20 526 1.00 MCS A 27 W/E08 EK3.4 27 1.00 MCS C 28 003 G2.2.36 528 1.00 MCS B 29 004 K6.27 529 1.00 MCS C 30 004 K5.09 30 1.00 MCS B 31 005 K5.05 31 1.00 MCS C 32 006 A2.05 532 1.00 MCS C 33 006 K6.18 33 1.00 MCS B 34 007 A1.01 534 1.00 MCS C 35 008 A3.08 35 1.00 MCS C 36 010 K2.01 36 1.00 MCS C 37 012 K1.05 237 1.00 MCS B 38 013 A4.01 538 1.00 MCS A 39 013 K3.03 39 1.00 MCS D 40 025 K5.01 40 1.00 MCS C 41 022 K3.02 41 1.00 MCS C 42 025 K4.02 542 1.00 MCS C 43 026 K4.07 543 1.00 MCS B 44 039 K1.01 44 1.00 MCS D 45 039 K4.02 545 1.00 MCS B 46 059 G2.1.32 546 1.00 MCS B 47 061 K3.01 547 1.00 MCS A Friday, March 04, 2016 10:20:11 AM 1

ANSWER KEY REPORT for 1603 NRC RO Exam Test Form: 0 Answers

ID Points Type 0 48 061 K6.01 48 1.00 MCS D 49 062 A3.04 49 1.00 MCS C 50 063 A4.01 550 1.00 MCS C 51 064 K2.02 551 1.00 MCS D 52 073 A1.01 52 1.00 MCS D 53 076 A2.01 53 1.00 MCS C 54 078 K2.02 54 1.00 MCS C 55 103 A3.01 55 1.00 MCS A 56 002 K3.03 556 1.00 MCS A 57 015 K2.01 57 1.00 MCS D 58 017 K1.01 258 1.00 MCS B 59 028 A1.02 59 1.00 MCS D 60 034 G2.4.31 60 1.00 MCS A 61 041 K6.02 61 1.00 MCS B 62 045 K5.23 162 1.00 MCS A 63 056 A2.04 63 1.00 MCS C 64 072 A3.01 564 1.00 MCS B 65 079 K4.01 65 1.00 MCS A 66 G 2.1.28 166 1.00 MCS A 67 G 2.1.30 67 1.00 MCS D 68 G 2.2.39 568 1.00 MCS C 69 G 2.2.43 69 1.00 MCS A 70 G 2.3.4 170 1.00 MCS C 71 G 2.3.11 571 1.00 MCS B 72 G 2.3.12 72 1.00 MCS D 73 G 2.4.21 173 1.00 MCS C 74 G 2.4.29 174 1.00 MCS C 75 G 2.4.46 75 1.00 MCS C SECTION 1 ( 75 items) 75.00 Friday, March 04, 2016 10:20:11 AM 2

References for 1603 NRC RD Exam

1. Steam Tables

2. Mollier Diagram

3. TRM figure 8.1.1-4

4. O-GO-15, Appendix U, rev 40

5. AOP-M.01, pages7&8rev28

ML16110A027

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